Vita - College of Engineering - The University of Tennessee, Knoxville

EDUCATION 

CURRICULUM VITAE 

LAURENCE F. MILLER 

Nuclear Engineering Department 

The University of Tennessee, Knoxville 

Kansas State University B.S. 1964 Nuclear Engineering 

Kansas State University M.S. 1966 Nuclear Engineering 

Carnegie-Mellon University 1967-68 Graduate Work (21 Hours) 

Texas A&M University Ph.D. 1976 Nuclear Engineering 

UNIVERSITY SERVICE 

American Nuclear Society Student Chapter Advisor (~1978-1982) 

Chair of the UTK Radiation Safety Committee (1989-2001, 2003-2006) 

Chair of the UTK Environmental, Health and Safety Committee (1997-present) 

Chair of the College of Engineering Promotion Tenure Committee (2002 & 2003) 

Member of the College of Engineering Promotion Tenure Committee (1999-2001) 

Member of the College of Engineering Curriculum Committee (various) 

Faculty Senate: Testing and Grading, Calendar, Legislative, and Educational Policy Committees (~1992- 

1995) 

Primary Author of the ABET Self Study Document for the Department of Nuclear Engineering (2000) 

Taught Tennessee Industries Week Short Courses on the Fuel Cycle, Radioactive Waste, or Radiological 

Assessment Almost Annually (1978-present) 

Advisory Board for the College of Engineering (COE) Basic Engineering Review Team 

PROFESSIONAL ACTIVITIES 

Chair of the Scholarship, Policy and Procedures Committee of the American Nuclear Society (2006-2009 

) 

Vice Chair of the Scholarship, Policy and Procedures Committee of the American Nuclear Society (2003- 

2006) 

Technical Programme Co-Chair of the ICRS-10 RPS 2004 International Meeting on Radiation Protection 

and Shielding held in Funchal, Madeira Island (Portugal) 9-14 May 2004 

National Program Committee of the American Nuclear Society (2001-2003) 

President of the East Tennessee Chapter of Health Physics, 2003 

Chair of the Radiation Protection and Shielding Division (2001-2002) 

General Chair for the Spectrum 2000 Meeting in Chattanooga (meeting attendance of about 400) 

Technical Program Chair for the Meeting in Nashville in June 1998 (Meeting Attendance of about 1000) 

Chair of the Oak Ridge/Knoxville Local Section (1996-1997) 

Distinguished Service Award for work on the 1982 Worlds Fair 

INTERNATIONAL PARTICIPATION 

Presentation of a paper at the IEEE Nuclear Science Symposium-Medical Imaging Conference in Dresden, 

Germany (19-25 October 2008) 

Presentation of a paper at the International Congress on Advanced in Nuclear Power Plants (ICAPP 2007) 

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in Nice France, May 13-18, 2007 

Presentation of two papers at a Conference on Neutron Dosimetry at Uppsala, Sweeden, 2006 

Presentation of a paper at a Conference on Radiation Protection at Venice, Italy, 2005 

Technical Programme Co-Chair of the ICRS-10 RPS 2004 International Meeting on Radiation Protection 

and Shielding held in Funchal, Madeira Island (Portugal) 9-14 May 2004 

Presentation of papers at a Conference on Neutron Capture Therapy at Essen, Germany in 2002 

Presentation of papers at a Conference on Neutron Capture Therapy at Osaka, Japan in 2000 

Presentation of papers at a Conference on Radiation Protection at Funchal, Madeira Island (Portugal) 2004 

Technical Collaboration with Staff at IPEN in Sao Paulo, Brazil on computational methods to improve 

accuracy of treatment planning for use of beam radiation to treat cancer. 

SOCIETIES(Current) 

American Nuclear Society 

Health Physics Society 

Tau Beta Pi 

Sigma Xi 

SOCIETIES (Not current) 

National Society of Professional Engineers 

American Society for Engineering Education 

International Society of Neural Networks 

HONORS 

Lilly Endowment Post-Doctoral Teaching Awards Fellowship 

Outstanding Service to the American Nuclear Society 

Technology for Energy Corporation Outstanding Teacher Award (1982) 

Departmental Outstanding Teacher Award (1983 - 1984) 

Departmental Outstanding Teacher Award (1986 - 1987) 

Outstanding College of Engineering Faculty Advisor Award (1996-1997) 

Departmental Outstanding Teacher Award (2003-2004) 

College of Engineering Research Fellow Award (April 2009) 

PERSONAL DATA 

Height: 6'1", Weight: 215 lbs., Marital Status: Married, Citizenship: USA by birth 

Clearances Held, not current: DOD Secret; AEC L; DOE L; DOE Q 

CURRENTLY FUNDED GRANTS 

1) National Science Foundation Grant, Academic Research Initiative, from September 15, 2008 through 

August 31, 2009 for $380,000 on Transformational Scintillation Materials for Neutron and Gamma 

Detectors and Education Integration. The proposal is for five years at $400,000 per year with funding 

through the Domestic Nuclear Detection Office and is renewable for four years upon satisfactory 

review. Co-PIs are Dayakar Penumadu and Chuck Melcher. 

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2) Nuclear Regulatory Commission through a subcontract for $35,000 from Southern University at 

Baton Rouge to assist in the development of an academic program in Nuclear Engineering. 

3) Contract with Savannah River National Laboratory for $30,000 to provide support in 

characterization of spent fuel casks. Graham Walford is a Co-PI. 

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PREVIOUSLY FUNDED RESEARCH 

1) Nuclear Regulatory Commission Grant from September 1, 2008 through May 31, 2010 for $150,000 

on the Development of Education and Training Materials for Environmental Assessments and Security 

of Nuclear Facilities. Seventy-five thousand is subcontracted to Missouri University of Science and 

Technology 

2) Department of Energy (DOE) Nuclear Energy Research Initiative (NERI) Program, Solicitation – DE- 

PS07-04ID141551, “Uncertainty Analyses of Advanced Fuel Cycles,” Award began January 2005 for 

$210,000 per year for three years and was extended with a final report due in December 2008. Work 

was in collaboration with Argonne National Laboratory. 

3) Nuclear Regulatory Commission Grant from September 1, 2007 through August 31, 2008 for 

$200,000 on the Development of Education and Training Materials for Environmental Assessments 

and Security of Nuclear Facilities. One hundred thousand is subcontracted to University of Missouri- 

Rolla. 

4) DOE Innovations in Nuclear Infrastructure and Education (INIE) Program through the Multi 

University Southeast INIE Consortium (MUSIC) through North Carolina State University (NCSU), 

“Internet Based Reactor Experiments, Reactor Simulations, and Neutronics Calculations for the 

PULSTAR Reactor at NCSU. Award begin September 9, 2003 for five years (currently a no cost 

extension). Total funding was about $300,000. 

5) DOE Innovations in Nuclear Infrastructure and Education (INIE) Program through the Multi 

University Southeast INIE Consortium (MUSIC) through North Carolina State University (NCSU), 

“Internet Based Reactor Experiments, Reactor Simulations, and Neutronics Calculations for the 

PULSTAR Reactor at NCSU. Award begin September 9, 2003 for five years. Funding for the first 

year was $50,000, the $75,000 for the second year and should be $100,000 for the following years. 

6) Tennessee Valley Authority (TVA), “Evaluations of Sustainable Nuclear Power Options,” October 1, 

2003 through December 31, 2004. Award was for $80,492. 

7) Tennessee Valley Authority (TVA), “Update of Advanced Nuclear Review,” October 1, 2003 through 

September 30, 2004. Award for $25,000 

8) Tennessee Valley Authority (TVA), “Advanced Nuclear Review,” October 1, 2002 through September 

30, 2003. Award for $112,000. 

9) Oak Ridge National Laboratory (ORNL), “Emerging Technologies for Commercial Reactors,” June 1, 

2004 through October 30, 2004. Award was for $15,000 

10) Co-PI, Department of Energy (DOE) Nuclear Energy Research Initiative (NERI) Program, Solicitation 

DE-FG03-00SF22168, “Design & Layout Concepts for Compact, Factory-Produced, Transportable 

Generation IV Reactor Systems,” July, 2000 through September 30 2003. Award was for about 

$215,000 per year for three years. My participation involved about one-third of the effort. 

11) Co-PI, Department of Energy (DOE) Nuclear Energy Research Initiative (NERI) Program, 

Identification Number N841016, Determination of Biodistribution of Boronated Amino Acids and 

BNCT Dosimetry Using Positron Emission Tomography,” Award varied form $150,000 to $200,000 

per year. October 1, 1997 through Sept 2000. My participation was about one-half the effort. 

12) ORNL & BWXT, from 1993 through 2000, approximately $150,000 per year. Records are not 

available. 

ESTIMATES OF OTHER PREVIOUSLY FUNDED RESEARCH 

Oak Ridge National Laboratory and other DOE Managed Facilities (~$1,000,000, early 1990s) 

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Tennessee Valley Authority (~$800,000, late 1980s) 

Waste Management Research and Education Institute ($223,192, early 1990s) 

International Technology Corporation ($12,043, early 1990s) 

Bechtel National Corporation (~$70,000, early 1990s) 

SENES Oak Ridge, Inc. (~$150,000, early 1990s) 

PROFESSIONAL EXPERIENCE 

1976-Pres. Department of Nuclear Engineering, University of Tennessee, Knoxville, TN. Teaching 

responsibilities at the undergraduate level include courses in Nuclear Reactor Theory, 

Nuclear Engineering Laboratory, Nuclear Fuel Management, and Nuclear Systems 

Dynamics and Control. Graduate level courses include Reactor Fuel Management, 

Management of Radioactive Materials, Radiation Monitoring and Dose Assessment, 

Uncertainty Analysis, Internal Dosimetry, and Medical Imaging. Research publications 

are in the area of instrumentation, control theory, neutronics, neural networks, health 

physics and radioactive waste. Directed research of sixty-seven M.S. and eleven Ph.D. 

students since 1988. 

1972-1976 Graduate School at Texas A&M University. Qualified as a Senior Reactor Operator and 

was responsible for operation and maintenance of the AGN-201 reactor, and supervised 

student laboratory experiments. 

1968-1972 Bettis Atomic Power Laboratory at Naval Reactor Facility near Idaho Falls, Idaho. 

Qualified as Engineering Officer of the Watch and trained Navy Personnel on the A1W 

Plant (Prototype of the Enterprise Reactors). 

1966-1968 Astronuclear Laboratory at Large Pennsylvania and Jackass Flats Nevada. Performed 

neutronics calculations and real time computer programming for nuclear rocket engine 

testing. 

BIOGRAPHICAL SKETCH 

Dr. Miller, began his professional career with Westinghouse Electric Corporation at the 

Astronuclear Laboratory near Pittsburgh, Pennsylvania. He gained experience in neutronics, real time 

programming in assembly language and operations. He transferred to the Bettis Atomic Power Laboratory 

at the Naval Reactor Facility and qualified as Engineering Officer of the Watch. He began his studies for 

his Ph.D. at Texas A&M in 1972. He qualified as a Senior Reactor Operator with the United States 

Nuclear Regulatory Commission and supervised students in reactor experiments at Texas A&M. After 

receiving his Ph.D. in 1976, he accepted a position with the Department of Nuclear Engineering at The 

University of Tennessee. 

Dr. Miller joined the faculty in 1976 and has made significant contributions to the academic and 

research programs in UTNE. Funding from a Radioactive Waste Management contract permitted 

renovations for laboratory space and for new laboratory equipment (1987), and he developed the Radiation 

Protection program begun in 1988 in collaboration with area professionals. Implementation of the 

Radiation Protection program involved the development of three new courses, coordination with adjunct 

faculty, and interaction with UT administration. He has directed the research of 76 M.S. students and 14 

Ph.D. students. He has taught short courses on Radiological Assessment, developed new special topics 

courses in Uncertainty Analysis and Medical Imaging, and participated in development of a Special Topics 

course on Internal Dosimetry. He has developed seven new courses for the UTNE and has managed 

several million dollars of research. 

Dr. Miller has received several teaching awards and an outstanding service award from the 

National American Nuclear Society. He was the advisor for the student section of the Health Physics 

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society for three years, which he organized through the national Health Physics Society and the UT 

administration, and he has served as the advisor for the student section of the American Nuclear Society. 

He has had several leadership positions with the local section of the American Nuclear Society, including 

the Chair for 1996-1997, and he was the Technical Program Chair for the June 1998 National ANS 

meeting. He served on the National Program Committee of the American Nuclear Society from 1999 

through 2001, he served as the General Chair for the Spectrum 2000 meeting, an International Conference 

on Nuclear and Hazardous Waste Management, and he served as chair of the Radiation Protection and 

Shielding Division of the American Nuclear Society (2001-2002). He served as co-chair of the 

Scholarship Policy and Coordination Committee (2003-2005) and is currently the chair. 

He has served the University of Tennessee Faculty Senate, on several university-wide committees, 

and on the Advisory Board for the College of Engineering (COE) Basic Engineering Review Team. He 

served as the Chairman of the University of Tennessee Radiation Safety Committee for 16 years and of the 

Environment Health and Safety Committee for about 10 years. He chaired the COE Promotion and Tenure 

Committee during 2001-2003 academic years, and he has served on the COE Awards Committee. 

His efforts during the first twelve years involved a substantial commitment to teaching nuclear 

engineering laboratory and reactor theory courses with a research focus primarily on radioactive waste 

management and radiation detection. After establishing the Radiation Protection program in 1988 his 

activities were refocused on topics involving radiological assessment and radiation detection with a lighter 

teaching load. More recently his research concentrates on traditional nuclear engineering topics. 

Results from his work on Boron Neutron Capture Therapy contribute to the understanding of how 

to improve protocols treatment of tumors. His work on detectors and methods for radiation detection 

include development of improved methods for utilization of pulse shape discrimination and of improved 

neutron detectors. He has recently completed studies for the Tennessee Valley Authority on the 

Sustainability of Nuclear and Alternative Energy Sources and on Advanced Reactor Designs for 

Implementation in the 2010 to 2015 time frame. His work on the development of internet-based reactor 

experiments for nuclear engineering students is reviewed in the January 2005 issue American Nuclear 

Society’s national news magazine. His current contract on evaluation of Uncertainties of Advanced 

Nuclear Fuel Cycles will facilitate decision making on the selection of reactors and fuel cycles that will 

provide reliable electrical energy for thousands of years. 

Calendar Year 2012 

PUBLICATIONS 

M. R. Williamson, L. Miller, and I. Sen, “Measurement and Modeling of Light Yield Non-Proportionality 

in Neutron Detectors,” Nuclear Technology (Vol 177, # 3, pp 413-420) 

Graham V. Walford, Sean J. Branney, David W Roberts, Raymond K. Maynard, Laurence F. Miller, 

Christoph C. Borel, David F .Bunker, John N. Dewes, “Enhancing Rapid Non Contact and 

Remote Sensing of Radionuclide Bearing Compounds, Our abstract (attached) has been accepted 

at INMM for presentation 

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K. Yang, M. Zhuravleva, M. Urffer, L. F. Miller and C. L. Melcher, Optical and scintillation properties of 

CsGd2Cl7:Ce 3+ for gamma and neutron detection, Nucl. Instr. Meth., A656, 92-95 (2011). 

Zhuravleva, M. Urffer, L. F. Miller and C. L. Melcher, Optical and scintillation properties of 

CsGd2Cl7:Ce 3+ for gamma and neutron detection, Nucl. Instr. Meth., A656, 92-95 (2011) 

Branney, S., Walford, G.V., Kulp, D., Hertel, N., Hanks, D.H., Miller, L.F., “A Gamma Ray Scanning 

Approach to Quantify Spent Fuel Cask Radionuclide Contents” 11-A-360-INMM-July 2011. 

Walford, G.V., Miller, L.F., Borel, C.C., Gross, K.E., Tuttle, R.F., Chapman, J.A., Gunning, J.E., “A 

Mobile Directional Gamma Ray Monitor System for Rapid Location of Radioactive Materials” 11- 

A-372-INMM July 2011 

Walford, G.V., Miller, L.F., Bogard, J.S., Chapman, J.A., Gunning, J.E., Krichinsky, Lousteau, A.L., 

Solodov, A.A., Branney, S., Perkins, J., Stein, J., “Evaluation of Gamma Ray Detector 

Performances for Differing Special Nuclear Material (SNM) Geometries” 11-A-391-INMM July 

2011 

M. R. Williamson, M. Urffer, and L. F. Miller, “Characterization of Neutron Detectors for DHS 

Applications,” Transactions of the American Nuclear Society, June 2011. 

I. Sen, D. Penumadu, M. R. Williamson, L. Miller, A. Green, and A. Mabe, Thermal Neutron Scintillator 

Detectors Based on Poly (2-Vinylnaphthalene) Composite Films, IEEE Trans. Nuclear Science, 

(Accepted, but in review). 


Jeff Preston and LaurenceF. Miller, “A Simulation and Uncertainty Analysis Tool forEvalluation of 

Nuclear Fuel Cycles,” Transactions of the American Nuclear Society (November 2010) 

Martin R. Williamson, Indraneel Sen, Alex Green, Dayakar Penumadu, and L. F. Miller, “Monte Carlo 

Modeling for Multivariate Optimization of Transformational Neutron Detectors”, Transactions of 

the American Nuclear Society (June 2010) 

Zheng Chang, A. Green, M. Williamson, G. Schweitzer, L. Miller, “A Systematic Study of Carborane- 

Loaded Organic Scintillators for the Detection of Neutrons” IEEE Nuclear Science Symposium- 

Medical Imaging Conference, Knoxville, TN (October, 2010) 

M. R. Williamson, I. Sen, A. Green, D. Penumadu, G. Schweitzer, and L. F. Miller, “Neutron Detector 

Optimization through Characterization and Modeling,” IEEE Nuclear Science Symposium-Medical 

Imaging Conference, Knoxville, TN (October, 2010) 

A. Green, M. Williamson, I. Sen, D. Penumadu, L. Miller, “A Novel Neutron Response Measurement System 

for Scintillation Material Characterization,” IEEE Nuclear Science Symposium-Medical Imaging 

Conference, Knoxville, TN (October, 2010) 

I. Sen, A.N. Mabe, A. Green, D. Penumadu, G. Schweitzer, K. Thomas, L. Miller, “Polymer Composite 

Thermal Neutron Detector,” IEEE Nuclear Science Symposium-Medical Imaging Conference, 

Knoxville, TN (October, 2010) 

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Trent L. Nichols, George W. Kabalka, Laurence F. Miller, Michael T. McCormack, and Andrew Johnson, 

“Implications for Clinical Treatment from the Micrometer Site Dosimetric Calculations in of 

Boron Neutron Capture Therapy”, Appl Radiat Isot, 67(7-8 suppl) S161-3 

J. Preston and L.F. Miller, “Management Tool for Uncertainty Analysis of Advanced Nuclear Fuel 

Cycles,” Transactions of the American Nuclear Society, (June 2009) 

Stephan Janson and Laurence Miller, “Heat Load Characteristics of Thorium Based Molten Salt Spent 

Fuel,” Transactions of the American Nuclear Society, (June 2009) 


Eric W. Abelquist, David King, and Laurence F. Miller, “An Approach for Addressing Hot Spots at 

Hazardous Waste Sites,” Journal of Risk Analysis (In review) 

Trent L. Nichols, George W. Kabalka, Laurence F. Miller, Michael T. McCormack and Andrew Johason. 

“Implications for Clinical treatment from the Microdosimetry,” International Conference on Neutron 

Capture Therapy, Florence, Italy (November 2009) 

Jeff Preston and L. F. Miller, “Reduction of Repository Heat Load Using Advanced Fuel Cycles,” 

International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource” 

Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19, 2008 

Dustin R. Osborne and Laurence F. Miller, “Startup and Shutdown Thermal Modeling of a Pressurized 

Water Reactor Simulator,” IEEE Nuclear Science Symposium, Dresden Germany (October 2008) 


L.F. Miller and Jeff Preston, “Digital Pulse Shape Discrimination,” Radiation Protection Dosimetry (2007) 

doi:10.1093/rpd/ncm052 

T.L. Nichols, L.F. Miller, G.W. Kabalka and T.M. Dudney, “Microdosimetric Study for Interpretation of 

Outcomes from Boron Neutron Capture Therapy Clinical Trials,” Radiation Protection Dosimetry (2007) 

doi:10.1093/rpd/ncm130 

L.F.Miller, J.Preston, Brian Thomas, J.McConn, J. Hou, T.Anderson,and M.Humberstone 

“Uncertainty Analysis Methods for Equilibrium Fuel Cycles,” Transactions of the American Nuclear 

Society, (June 2007) 

L. F. Miller, T. Anderson, J. Preston, M. Humberstone, J. Hou, J. McConn, and Luc Van Den Durpel 

"Evaluation of Various Fuel Cycles to Control Inventories of Plutonium and Minor in Advanced Fuel 

Cycles" Proceedings of ICAPP 2007 Nice, France, May 13-18, 2007 Paper 7288 

Thomas Anderson, Jeff Preston, Luc Van Den Durpel, L.F. Miller, “Uncertainty Analysis of Advanced 

Fuel Cycles Using Dynamic System Modeling,” Transactions of the American Nuclear Society, 

(November 2007) 

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Matt Humberstone, Jeff Preston, L.F. Miller, “Isotopic Composition of Spent Fuel from Advanced Burner 

Reactors as a Function of Burnup,” Transactions of the American Nuclear Society, (November 2007) 

J. Preston, M. Humberstone, T. Anderson, and L.F. Miller “Repository Uncertainty Analysis for Advanced 

Fuel Cycles,” Transactions of the American Nuclear Society, (November 2007) 

Jeff Preston, B. Thomas, T. Anderson, M. Humberson, J. Hou, S. Frederiksen,J. McConn, and L.F. Miller, 

“Assessments of Uncertainties in Advanced Equilibrium Fuel Cycles,” GLOBAL 2007, Advanced Nuclear 

Fuel Cycles and Systems, September 9-13, Boise, Idaho (September 2007) 

Dustin Osborne, Jia Hou, Gary Graves and Laurence Miller, “Development of a Modern Pressurized 

Water Reactor Simulator: Instrumentation, Design and Data Acquisition,” 2007 IEEE Nuclear Science 

Symposium Conference Record, N15-179, October 27 – November 3, 2007, Honolulu, Hawaii 


L. Miller, R. Pevey, W. Hines, L. Townsend, B. Upadhyaya, P. Groer, M. Grossbeck and H. Dodds, 

“Innovations in Nuclear Engineering Distance Education at The University of Tennessee,” PHYSOR-2006 

Advances in Nuclear Analysis and Simulation (Sept 2006) 

L.F. Miller and Jeff Preston, “Digital Pulse Shape Discrimination,” Tenth Symposium on Neutron 

Dosimetry,” Uppsala, Sweden (June 2006) (Accepted for publication in Radiation Protection Dosimetry) 

T. L. Nichols, L. F. Miller, and G. W. Kabalka, “Microdosimetric Study for Interpretation of Outcomes 

from Boron Neutron Capture Therapy Clinical Trials,” Tenth Symposium on Neutron Dosimetry,” 

Uppsala, Sweden (June 2006) (Accepted for publication in Radiation Protection Dosimetry) 

Jeff Preston, Jeff Clark, Gary Seweder, F.R. Mynatt and L.F. Miller, “The Influence of Fuel Cycle and 

Spent Fuel Characteristics on Repository Heat Loads,” Transactions of the American Nuclear Society, 

(June 2006) 

Matthew L.F. Miller, R. E. Pevey, L. F. Miller and A. I. Hawari, “Lifetime Predictions for Three Fuel 

Reloading Scenarios in the PULSTAR Reactor at NCSU,” Transactions of the American Nuclear Society, 

(June 2006) 

Mark S. Wyatt, Laurence F. Miller, “A Comparison of Monte Carlo and Model-Based Dose Calculations 

in Radiotherapy Using MCNPTV,” Nuclear Instruments and Methods in Physics Research A 562 (2006) 

1013-1016 

L.F.Miller, J. Preston, T. Anderson, J. McComm, F.R. Mynatt, and Luc Van Den Durpel, “Utilization of 

Fast Reactors to Control Inventories of Plutonium and Minor Actinides in Advanced Fuel Cycles” 

Transactions of the American Nuclear Society, (November 2006) 


L.F. Miller, M.F. Fontana, Ricky Summit, Igor Petrusky, Matthew Miller and Scott Outten, Advanced 

Nuclear Plant Review Update for Tennessee Valley Authority Contract Report, Department of Nuclear 

9

Engineering, The University of Tennessee, February 2005 

L.F. Miller, Robert E. Uhrig, Mario Fontana, Vijaya Kantubhukta, Matthew Miller, and Scott Outten, 

Sustainable Production of Power Using Nuclear and Alternative Energy for Tennessee Valley Authroity 

Contract Report, Department of Nuclear Engineering, The University of Tennessee, April 2005 

A.C. Stephan and L.F. Miller, "Micromegas Neutron Beam Monitor Neutronics", Radiation Protection and 

Dosimetry (2005), Vol. 115, No. 1-4, pp 357-362 doi:10.1093/rpd/nci101 

R. Pevey, L.F. Miller, B.J. Marshall, L.W. Townsend and B. Alvord, "Shielding for a Cyclotron used 

for Medical isotope Production in China," Radiation Protection and Dosimetry (2005), Vol. 116, No. 1-4, 

pp 415-419 doi:10.1093/rpd/nci206 

A.C. Stephan, D. Dai, S.A. Wallace and L.F. Miller, "Modeling of Composite Neutron Scintillators," 

Radiation Protection and Dosimetry (2005), Vol. 116, No. 1-4, pp 165-169 doi:10.1093/rpd/nci121 

M. Wyatt, C. Corredor, M. Tamimi and L.F. Miller "Comparison of Treatment Planning Dose Calculations 

with Measurements and Monte Carlo Calculations in a RANDO Phantom," Radiation Protection and 

Dosimetry (2005), Vol. 116, No. 1-4, pp 461-465 doi:10.1093/rpd/nci203 

T.L. Nichols, L.F. Miller and G.W. Kabalka, "Using Microdosimetry to Understand the Clinical 

Outcomes of Boron Neutron Capture Therapy," Radiation Protection and Dosimetry (2005), Vol. 116, No. 

1-4, pp 466-469 doi:10.1093/rpd/nci248 

R. Pevey, L.F. Miller, B.J. Marshall, L.W. Townsend and B. Alvord, “Efficacy of Three-Dimensional 

Adjoint Biasing for a Cyclotron Used for Medical Isotope Production in China,” 12th International 

Symposium on Reactor Dosimetry, Gattlinburg, Tennessee (April, 2005) 

L. F. Miller, Luc Van Den Durpel, A.M. Yacout, F.R. Mynatt, G. Sweder, T. Anderson, Robert Hill, 

“Methodology for Uncertainty Analysis of Advanced Fuel Cycles and Preliminary Results,” Transactions 

of the American Nuclear Society, (November 2005) 

L.F. Miller, R.E. Pevey, M.L. Miller, A.I. Hawari, “Determination of Power Peaking Factors for 

Replacement Fuel for the PULSTAR Reactor at NCSU,” Transactions of the American Nuclear Society, 



A. Iulian Apostoaei and Laurence F. Miller, “Uncertainties in Dose Coefficients From Ingestion of 131 I, 

137 Cs, and 90 Sr,” Health Physics Vol. 86, No.5, May 2004 

Andrew C. Stephan, Ronald G. Cooper, Laurence F. Miller, “Monte Carlo Studies of a Micromegas 

Neutron Beam Monitor,” Nuclear Instruments and Methods in Physics Research A 521 (2004) 441-453 

L.F. Miller, R.E. Uhrig, V. Kantubhukya, S.S. Outten, M.L.F. Miller, M.H. Fontana, and R.D. Boroughs, 

“Sustainability of Nuclear and Alternative Energy Sources,” Transactions of the American Nuclear 

Society, (November 2004) 

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A.I. Hawari, M.I. Al-Sheikhly, M.A. Garland, N.E. Hertel, L.F. Miller and S.I. Miller, “Multi-University 

Southeast INIE Consortium: First Year Highlights and Successes,” Transactions of the American Nuclear 


L.F. Miller, A.I. Hawari, and A. Cook, “Internet University Reactor Experiments for Education in Nuclear 

Engineering,” Transactions of the American Nuclear Society, (November 2004) 

M.S. Wyatt and L.F. Miller, “MCNPTV: Implementation of a Methodology for Converting CT Images to 

MCNP Input,” Transactions of the American Nuclear Society, (November 2004) 

T.L. Nichols, L.F. Miller, and G.W. Kabalka, “The Micordosimetry of boron neutron capture therapy in an 

ellipsoidal cell geometry,” Eleventh World Congress on Neutron Capture Therapy, (October 2004) 

L.F. Miller, A. Rahim, M.D. Khan, T.L. Nichols and G.W. Kabalka, “Recommended Infusion Protocol for 

Neutron Capture Therapy,” Eleventh World Congress on Neutron Capture Therapy, (October 2004) 


George Kabalka, Trent L. Nichols, Gary T. Smith, Laurence F. Miller, Mohammad K. Khan and Paul M. 

Busse, “The use of positron emission tomography to develop boron neutron capture therapy treatment 

plans for metastatic malignant melanoma,” Journal of Neuro-Oncology 62: 187-195, 2003 

Steven Wallace, Andrew C. Stephan, Phillip C. Womble, Gavi Begtrup, Laurence F. Miller, Sheng Dai, 

“Active Interrogation of Fissile Material Using an SBD,” submitted to Nuclear Instruments and Methods in 

Physics Research A, in press. 

T.L. Nichols, L.F. Miller, G.W. Kabalka, “New Insights in the Micro-Dosimetry of Boron Neutron 

Capture Therapy Using a Monte-Carlo Technique,” Transactions of the American Nuclear Society, (June 

2003) 

A. I. Hawari, S. I. Miller, N. E. Hertel, M. Al-Sheikhly, L. F. Miller, A. E. Bayoumi, “Multi-University 

Southeast INIE Consortium,” Transactions of the American Nuclear Society, (November 2003) 

M.H. Fontana, L.F. Miller, R. Borroughs, S. Outten, M. Miller, and I. Petruski, “Assessment of Power 

Reactors for Implementation in the 2010-2015 Time Frame,” Transactions of the American Nuclear 


L.F. Miller, M.F. Fontana, Scott Outten, Igor Petrusky, and Matt Miller, Advanced Nuclear Plant Review 

for Tennessee Valley Authority, Contract Report (December 2003) 


Steven Wallace, Andrew C. Stephan, Laurence F. Miller, Sheng Dai, “Neutron detector based on Lithiated 

sol-gel glass,” Nuclear Instruments and Methods in Physics research A 483 (2002)764-773 

T. L. Nichols, G. W. Kabalka, L. F. Miller, M. K. Khan, and G. T. Smith, “Improved Treatment Planning 

for Boron Neutron Capture Therapy for Glioblastoma Multiforme Using Fluorine-18 Labeled 

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Boronophenylalanine and Positron Emission Tomography, Medical Physics, 29(10), 2351-8, 2002 

A.C. Stephan, T. Gaulden, A.D. Brown, M. Smith, L.F. Miller, and T. Thundat, “Microcantilever 

Charged Particle Flux Detector,” Review of Scientific Instruments, Vol 73, Number 1 (January 2002) 

A. S. Icenhour, L. M. Toth, G. D. Delk Cul, L. F. Miller, “Gamma Radiolysis Studies of Uranyl Fluoride,” 

Radiochimica Acta Issue 2 Vol. 90 (2002) 

"The Use of Information Technology in The University of Tennessee Nuclear Engineering Distance 

Education Program", by J.W. Hines, L.F. Miller, R.E. Pevey, L.W. Townsend, B.R. Upadhyaya, R.H. 

Jackson, and H.L. Dodds, 2002 ASEE Annual Conference & Exposition, Montréal, Quebec, Canada, June 

16-19, 2002. 

Laurence Miller, Mohammad Khan, Wesley Williams, and Fred Mynatt, “Evaluation of two 300 MWe 

Fourth Generation PbBi Reactor Concepts,” ICONE 10: Tenth International Conference on Nuclear 

Engineering (April 2002) 

M.K. Khan, L. F. Miller, A. Abdul-Raheem, G.W. Kabalka, and T.L. Nichols, “Improving Existing BNCT 

Radiation Dosimetry by Use of Registered 18F-BPA PET and T1 Weighted MRI Images,” 12 th Biennial 

RPSD Topical Meeting of the American Nuclear Society (April 2002) 

Robbie Alhakeem and L. F. Miller, “Measurements of 6 MV and 18 MV Bremstralung Spectra from 

Varian 6100 and 2100 CD X-Ra Machines, Transactions of the American Nuclear Society, (June 2002) 

L. F. Miller, M. K. Khan, M. Williamson, W. Williams, F. R. Mynatt, “Evaluation of a PbBi Slab Reactor 

Core and Plant Layout,” Transactions of the American Nuclear Society, (November 2002) 

L.F. Miller and H. L. Dodds, “The University of Tennessee Department of Nuclear Engineering ABET 2000 

Visit,” Transactions of the American Nuclear Society, (November 2002) 

L. F. Miller, Abdul Rahim, M.K. Khan, T.L. Nichols, G.W. Kabalka, “Effects of Boron Self Shielding on 

BNCT Tumor Dose” Research and Development in Neutron Capture Therapy: Proceedings of the 10 th 

International Congress on Neutron Capture Therapy for Cancer, Essen, Germany, 8-13 September, 2002 

M.K. Khan, L. F. Miller, T.L. Nichols and G.W. Kabalka, “Use of Registered 18F-BPA PET Images to Enhance 

BNCT Treatment Planning,” Research and Development in Neutron Capture Therapy: Proceedings of the 10 th 


T. Nichols, L. Miller and G. Kabalka, “The Dependence of the Microscopic Dose in Boron Neutron Capture 

Therapy on Cell Geometry and Boron Content,” Research and Development in Neutron Capture Therapy: 

Proceedings of the 10 th International Congress on Neutron Capture Therapy for Cancer, Essen, Germany, 8-13 

September, 2002 

L. F. Miller, Abdul Rahim, M.K. Khan, T.L. Nichols, G.W. Kabalka, “Biokinetics of Varous Infusion Protocols 

for Neutron Capture Therapy,” Research and Development in Neutron Capture Therapy: Proceedings of the 10 th 



12

M. I. Zougari, L. F. Miller, and F. Mynatt, “A Dynamic Model for Generation IV Reactors,” Transactions 

of the American Nuclear Society 2001 Annual Meeting Milwaukee, Wisconsin, June 17-21, 2001 

B. J. Marshal and L. F. Miller, “Power Distribution Calculations for Various Tantalum Loadings in the 

HFIR Control Blades,” Transactions of the American Nuclear Society 2001 Annual Meeting Milwaukee, 

Wisconsin, June 17-21, 2001 

Andrew Stephan, S. Wallace, P. Womble, L. Miller, S. Dai “Evaluation of Lithiated Sol-Gel Glass 

Neutron Detector,” Abstracts of Papers Presented at the Forty-Sixth Annual Meeting of the Health Physics 

Society, Cleveland, Ohio (June, 2001) 

Andrew C. Stephan, Steven A. Wallace, Phillip C. Womble, Gavi Begtrup, Laurence F. Miller, "Assay of 

Fissile Material Using a Sol-Gel Coated SBD," Transactions of the American Nuclear Society, 2001 

Winter Meeting Reno, Nevada, November 11-15, 2001 

P.G. Groer, J.W. Hines, R. H. Jackson, L. F. Miller, R. E. Pevey, L. W. Townsend, B. R. Upadhyaya, H. 

L. Dodds, "Distance Education Programs in Nuclear Engineering at The University of Tennessee," 

Transactions of the American Nuclear Society, 2001 Winter Meeting Reno, Nevada, November 11-15, 

2001 


L.F. Miller, L.W. Townsend and C.W. Alvord, “Characterization of Neutron and Photon Sources from a 

10.5 MeV Proton Beam on [18O] Enriched Water,” Applications of Accelerators in Research and 

Industry – Sixteenth Int’l Conf. Edited by J.L. Duggan and I.L. Morgan (2001 Copyright, American 

Institute of Physics 0-7354-0015-6/01) 

T. Nichols, G. Kabalka, M. Khan, B. Das. S. Das. W. Bao and L. Miller, “The Development and 

Preliminary Testing of News Boronated Agents for BNCTD Based on PET Derived Data,” Ninth 

International Symposium on Neutron Capture Therapy for Cancer, Osaka International Convention Center, 

Osaka, Japan, October 2-6, 2000 

L. F. Miller, G. Kabalka, M. Khan,A. Rahim, T. Nichols, M. Wyatt, J. Thie, G. Smith, and I. Apostoaei, 

“Use of Positron Emissin Tomography for Determination of Tissue Specific Kinetics,” Ninth International 

Symposium on Neutron Capture Therapy for Cancer, Osaka International Convention Center, Osaka, 

Japan, October 2-6, 2000 

G. Kabalka, T. Nichols, G. Smith, L. Miller, and M. Khan, “The Use of Positron Emission Tomography in 

BNCT Treatment Planning for Metastatic Malignant Melanoma and Glioblastoma Multiforme,” Ninth 



T. E. Byrne, M. K. Khan, G. W. Kabalka, J. A. MacCabe, R. C. Martin, and L. F. Miller, “A study of the 

Induction of Chromosomal Aberrations in Human Breast Cancer Cells with Calibornium-252,” Ninth 



13

L. F. Miller, M. K. Khan, Abdul Rahim, G. W. Kabalka, T. F. Nichols, J. A. Thie, and G. T. Smith, “Use 

of Positron Emission Tomography to Determine Cellular-Level Kinetics of F-18 Tagged Phenylalanine,” 

Radiation Protection for Our National Priorties: Medicine, the Environment and the Legacy, Sponsored 

by: ANS Radiation Protection and Shielding Division and HPS Columbia Chapter, Spokane, Washington, 

September 17-21, 2000 

L. F. Miller, G. Kabalka, M. Khan, A. Rahim, T. Nichols, J. Thie, and G. Smith, “Determination of Tissue 

Specific Kinetics to Improve Boron Neutron Capture Therapy,” American Radiation Safety Conference 

and Exposition, Health Physics Society’s 45 th Annual Meeting, Denver Convention Center, Denver 

Colorado, June 25-29, 2000 

Brian Oakley, Doug Turner, and Laurence F. Miller, “Determination of Pre-irradiated Fissile Content for 

Oak Ridge SNF,” Spectrum 2000 International Conference on Nuclear and Hazaradous Waste 

Management, The Premier Nuclear and Hazardous Waste Management International Conference and 

Exposition, Chattanooga, TN September 24-28, 2000 

Laurence Miller, Mark Buckner, Jim Hylton and Jeff Chapman, “Radiation Measurements for Remediation 

of the Molten Salt Reactor,” Spectrum 2000 International Conference on Nuclear and Hazaradous Waste 



Laurence Miller, Lien Nguyen and Jeff Chapman, “Characterizatin ofTransuranic Waste from Gamma 

Spectroscopy Measurements,” Spectrum 2000 International Conference on Nuclear and Hazaradous Waste 



Steven Wallace, Andrew Stephan, Laurence Miller, and Sheng Dai, “Neutron Detection Using a Li-B 

Loaded Sol-Gel Glass,” Spectrum 2000 International Conference on Nuclear and Hazaradous Waste 



Keith Waggoner and L. F. Miller, “Neutron Shielding Effectiveness of Goethite Concrete,” 2000 

ANS/ENS International Meeting with cooperation from NEI, Washington D. C. November 12-16, 2000 

L. F. Miller, M. K. Khan, G. W. Kabalka, T. F. Nichols, G. T. Smith, A. Rahim, M.S. Wyatt, A. I. 

Apostoaei, C. A. Large, “Positron Emission Tomography-Based Dosimetry for Boron Neutron Capt ure 

Therapy,” 2000 ANS/ENS International Meeting with cooperation from NEI, Washington D. C. November 

12-16, 2000 

Trent L. Nichols, Laurence F. Miller, George W. Kabalka, Gary T. Smith, and Mohammad K. Khan, 

“Clinical Observations of Four Patients Who Have Undergone Positron Emission Tomography Scanning 

and Boron Neutron Capture Therapy,” 2000 ANS/ENS International Meeting with cooperation from NEI, 

Washington D. C. November 12-16, 2000 

S. A. Wallace, J. M. Hiller, Sheng, Dai, and L. F. Miller, “Neutron Detection Based Upon a Lithiated Sol- 

Gel Glass,” Applied Radiation and Isotopes 53 (2000) 755-758 Pergamon 

William E. Booker, Jr. Lecture Series, "Neutron Capture Therapy in the 21 st Century," Morrison's 

14

Conference Center The University of Tennessee Medical Center, Knoxville, TN February 18, 2000 


B. A. Thomas, F. O. Hoffman and L. F. Miller, "Health Risks from Radionuclides Released into the Clinch 

River," Transactions of the American Nuclear Society (June 1999) 

Emran Dawoud and L. F. Miller, "A Convolution Integral Approach for Performance Assessments with 

Uncertainty Analysis," Transactions of the American Nuclear Society (June 1999) 

Mohammad K. Khan, L. F. Miller, George F. Kabalka and Trent F. Nichols, "Use of PET to Improve 

Dosimetry for BNCT," Transactions of the American Nuclear Society (June 1999) 

L. F. Miller, Mark Buckner and Mike Buchanan, "Measurement of the Axial Distribution of Radioactivity 

in the Auxiliary Charcoal Bed of the Molten Salt Reactor Experiment at ORNL," Transactions of the 

American Nuclear Society (November 1999) 

M. S. Wyatt, L. F. Miller and H. L. Dodds, "Subcritical Reactivity Experiment for an Undergraduate 

Nuclear Engineering Laboratory," Transactions of the American Nuclear Society (November 1999) 

H. M. Moussa, L. Townsend and L. F. Miller, 'Manual Calibration of Liquid Scintillation Counter Using 

the Channel Ratio Technique," Transactions of the American Nuclear Society (November 1999) 

R. B. Sparks, L. F. Miller and K. F. Eckerman, "Automatic Identification of Organ/Tissue Regions in CT 

Image Data for Treatment Planning in Cancer Therapy," Proceedings of the Health Physics Society 1999 

Annual Meeting (June 1999) 

Nithyananda G. Narayana and L. F. Miller, "Neural Networks for Parameter Identification in 

Compartmental Models," Proceedings of the Sixth International Radiopharmaceutical Dosimetry 

Symposium, (January 1999) 

Aydogan B, Sparks RB, Stubbs JB, and Miller LF, "Uncertainty Analysis for Absorbed Dose from a Brain 

Receptor Imaging Agent," Proceedings of the Sixth International Radiopharmaceutical Dosimetry 

Symposium, (January 1999) 

M. Khan, L. Miller, G. Kabalka, T Nichols K. Hubner, and G. Smith, "Comparisons of Dosimetry for 

Boron Neutron Capture Therapy," Medical Physics, Vol. 26, No. 5, (June 1999) 

R Alhakeem, L. Miller, C. Ramsey and A. Oliver, "Determination of Bremstralung Soectra of High-Energy 

Medical Linear accelerators Using a Simpson Iteration Technique," Medical Physics, Vol. 26, No. 5, (June 

1999) 

S. A. Wallace, J. M. Hiller, Sheng Dai and L. F. Miller, “Neutron Detection Based Upon a Lithiated Sol 

Gel Glass,” Proceedings of IRMMA-99 Conference, October 1999 

Long K. Yong, Laurence F. Miller An Efficient Limit State Approach for Performance Assessment 

Uncertainty Analysis, Transactions of the American Nuclear Society (June 1998) 

15

B. A. Thomas, F. O. Hoffman and L. F. Miller, "Health Risks from Radionuclides Released into the Clinch 

River," Transactions of the American Nuclear Society (June 1999) 


Materials and PSD Methods by Nuclear Instruments and Methods in Physics 

Research (A) 416, pp 32-44(1998) 

Research(A) 416, pp 438-445 (1998) 

16 

Nuclear Instruments and Methods in Physics 

R.C. Martin, T.E. Byrne, and L.F. Miller, "Biomedical Neutron Research at the Californium User Facility for 

Neutron Science," Journal of Radioanalytical and Nuclear Chemistry, Vol. 236, Nos1-2 (1998) 5-10 

G. W. Kabalka, T. L. Nichols, G. T. Smith, K. F. Hubner, L. F. Miller, In Vivo Detection of Neutron 

Capture Therapy Agents Using Tomography, Transactions of the American Nuclear Society (June 1998) 

H. M. Moussa, L. Townsend, L. F. Miller, Determination of Radon Daughter Concentrations Using an 

Air-Sampling Technique, Transactions of the American Nuclear Society (June 1998) 

L. F. Miller, Lien Nguyen, Darryl Downing, Jeff Chapman, Lance Weems, F. J. Homan, Characterization 

of Transuranic Waste from Gamma Spectroscopy Measurements, Transactions of the American Nuclear 

Society (June 1998) 

D. L. Marsh, L. F. Miller, W. Bond, R. C. Martin, L. K. Felker, R. W. Whan, G. K. Schweitzer, 

“Optimization of Solvent Extraction Cycles to Separate Plutonium and Neptunium,” Transactions of the 

American Nuclear Society (June 1998) 


Alan S. Icenhour, M. Lynn Tharp and L. F. Miller, Time-Dependent Sensitivity Analysis of the 

SOURCE1 Computer Code, Transactions of the American Nuclear Society (June 1997) 

Alan S. Icenhour, Herschel W. Godbee and L. F. Miller, Radiolytic Gas Generation Estimates in 

Multiphase Systmes, Transactions of the American Nuclear Society (June 1997) 

L. F. Miller, L. D. Weems, Zhong Cao, Sedat Goluoglu, R. E. Pevey and H. L. Dodds, 

Placement of Criticality Alarms in the Paducah Gaseous Diffusion Plant Laboratory, Transactions of the 

American Nuclear Society (November 1997) 

Zhong Cao, L. F. Miller and M. A. Buckner, Dynamic Bias for Neutron-Photon Pulse Shape 

Discrimination by Using Neural Network and Bayesian Classifiers, Transactions of the American 

Nuclear Society (November 1997) 

H. M. Moussa and L. F. Miller, “Estimation of Uncertainty in Multigroup Diffusion Theory Results Using 

Functional Analysis,” Transactions of the American Nuclear Society (November 1997)

Lien Nguyen and L. F. Miller, "Characterization of Radiochemical Engineering Development Center 

Transuranic Waste at Oak Ridge National Laboratory," Proceedings of the Health Physics Society 1997 


Kyle Kleinhans and L. F. Miller, A Comparison of Field Screening Measurements and Laboratory 

Analysis for Uranium Contaminated Soils at the Alba Croft Facility and Vicinity Properties, Proceedings 

of the Health Physics Society 1997 Annual Meeting (June 1997) 

T. E. Byrne and L. F. Miller, Determination of Uptake and Efficacy of Compounds for Boron Neutron 

Capture Therapy, Proceedings of the Health Physics Society 1997 Annual Meeting (June 1997) 

Z. Cao and L. F. Miller, Evaluation of a Dynamic Bias Technique in Neutron-Photon Pulse Shape 

Discrimination by Using a Neural Network Classifier, Proceedings of the Health Physics Society 1997 


J. A. Chapman, D. C. Hensley, P. C. Womble and L. F. Miller, Detection Limits in Active-Neutron 

Devices for Assay of Fissile Material, Proceedings of the Health Physics Society 1997 Annual Meeting 

(June 1997) 

L. F. Miller, L. D. Weems, Zhong Cao, Sedat Goluoglu, R. E. Pevy and H. L. Dodds, Placement of 

Criticality Alarms in the Paducah Gaseous Diffusion Plant Laboratory, KY/G-639, Rev. 1, Department of 

Nuclear Engineering, The University of Tennessee (May 1997) 

L. K. Nguyen, L. F. Miller and D. J. Downing, Measurements of Fission and Activation Products for Oak 

Ridge National Laboratory Transuranic Waste Characterization, ORNL/TM-13292, National Technical 

Information Service, Department of Commerce, Springfield VA 22161 (June 1997) 


Zhong Cao, L. F. Miller and J. T. Mihalczo, "Total Cross Section Neutron Time-of-Flight Measurements 

with a Cf-252 Source as a Nuclear Engineering Laboratory Experiment," Transactions of the American 

Nuclear Society (June 1996) 

Z. Cao, M.A. Buckner and L. F. Miller, "Neutron-Photon Pulse Shape Discrimination for Radiation 

Survey Instruments," Proceedings of the Health Physics Society 1996 Annual Meeting (July 1996) 

Z. Cao and L. F. Miller, "Evaluation of Phoswich Detectors for Simultaneous Detection of Alpha, Beta and 

Photon Radiation," Proceedings of the Health Physics Society 1996 Annual Meeting (July 1996) 

B. Aydogan, R. B. Sparks, J. B. Stubbs, and L. F. Miller, "Estimation of Absorbed Dose Uncertainties Due 

to the Parameter Estimation and Inter-Patient Biokinetic Variabilities," Proceedings of the Health Physics 

Society 1996 Annual Meeting (July 1996) 

Y. Feng, L. F. Miller and S. M. Bartell, "Radioecological Exposure Assessment for the Chernobyl Cooling 

Pond (Lake) with Hydrodynamic Impacts," Proceedings of the Health Physics Society 1996 Annual 

Meeting (July 1996) 

17

K. M. Spenser, D. E. White and L. F. Miller, "Uncertainty Analyses for Radiological Assessments of St. 

Louis FUSRAP Sites," Proceedings of the Health Physics Society 1996 Annual Meeting (July 1996) 

L. F. Miller, "Neutron-Photon Pulse Shape Discrimination," Measurement and Control Engineering Center 

Industrial Advisory Board Meeting, (April, 1996) 

L. F. Miller, "Neutron-Photon Pulse Shape Discrimination," Measurement and Control Engineering Center 

Industrial Advisory Board Meeting, (October 1996) 


K. L. Ausbrooks and L. F. Miller, "Non-Destructive Assay of Drum Package Radioactive Waste Utilizing 

Tomographic Gamma Scanning," Proceedings of the Health Physics Society 1995 Annual Meeting (June 

1995) 

J. L. Brook, R. B. Gammage, K. E. Myer, and L. F. Miller, "Non-Conventional Passive Sensors for 

Monitoring Tritium on Surfaces," Proceedings of the Health Physics Society 1995 Annual Meeting (June 

1995) 

D. F. French, W. L. Bryan, and L. F. Miller, "Performance Evaluation of a Continuous Air Monitor," 

Proceedings of the Health Physics Society 1995 Annual Meeting (June 1995) 

E. B. Ripley and L. F. Miller, "Design Improvements in an Alpha Scintillation Detector," Proceedings of 

the Health Physics Society 1995 Annual Meeting (June 1995) 

J. R. Russell, M.G. Stabin, J. B. Stubbs, E. E. Watson, and L. F. Miller, "Radiation Absorbed Dose to the 

Embryo/Fetus from Nuclear Medicine Procedures," Proceedings of the Health Physics Society 1995 


N. W. Richards, D. J. Downing, J. R. Watts, L. F. Miller, G. R. Rao, and G. T. Mei, "Prediction of 

Compton Backgrounds in the Plutonium and Americium Regions of Phoswich Lung Count Spectra," 


E. K. Algutifan, E. Bailiff, and L. F. Miller, "Assessment of Off-Site Radiological Hazards at the Oak 

Ridge K-25 Site," Proceedings of the Health Physics Society 1995 Annual Meeting (June 1995) 

T. S. Kroodsma and L. F. Miller, "Radiation Dose Assessment for Plutonium Contamination at Area 13 of 

the Nevada Test Site Using Nevada Applied Ecology Group Data and the RESRAD Code," Proceedings 

of the Health Physics Society 1995 Annual Meeting (June 1995) 

D. W. Burkett, L. F. Miller, and G. K. Schweitzer, "Evaluation of Acid Digestion and Potassium Fluoride 

Fusion Procedures for Assaying Uranium in Soil," Proceedings of the Health Physics Society 1995 


Alan S. Icenhour, Herschel W. Godbee and L. F. Miller, "Low-Level Radioactive Waste Performance 

18

Assessments: Source Term Modeling," Transactions of the American Nuclear Society (June 1995) 

D. L. Feldman, L. Miller and M. E. Castle, "Evaluating the Acceptability of Soil Treatment Methods in the 

Department of Energy's Formerly Utilized Sites Remedial Action Program: A Stakeholder Analysis," 

Waste Management 95: HLW, LLW and Mixed Waste - Working Toward a Cleaner Environment, 

February, 26 - March 2, 1995, Tucson Arizona 


J. B. Miller, L. F. Miller and T. L. Hatmaker, "Development of a Field Method for the Detection of 

Technetium-99 in Soil," Proceedings of the Health Physics Society 1994 Annual Meeting (June 1994) 

B. S. Johnson and L. F. Miller, "A Radiological Assessment of Two Operable Units at the Rocky Flats 

Plant," Proceedings of the Health Physics Society 1994 Annual Meeting (June 1994) 

E. B. Lee, J. S. Bogard, W. H. Casson and L. F. Miller, "Accident Dosimetry Using Lithium Tetraborate," 


C. B. Pomatto, G. T. Mei and L. F. Miller, "Modeling the Response of an Albedo Neutron Dosimeter 

Using MCNP," Proceedings of the Health Physics Society 1994 Annual Meeting (June 1994) 

M. A. Buckner, C. S. Sims and L. F. Miller, "Improving the Performance of the Combination Personal 

Neutron Dosemeter," Radiation Protection Dosimetry, Vol. 51 No. 1 pp 5-15 (1994) 

David Feldman, Larry Miller and Martha Castle, "Evaluating the Acceptability of Soil Treatment Methods 

in the Department of Energy's Formerly Utilized Sites Remedial Action Program: A stakeholder Analysis," 

Energy Environment, and Resources Center, The University of Tennessee-Knoxville (September, 1994) 

Bruce Clemens, T. N. McGalliard, L. F. Miller, and T. W. Kerlin, "Establishing Cleanup Standards for 

Radioactive Scrap Metal," The Energy, Environment, and Resources Center, The University of Tennessee 

(March 1994) 


L.J. Nugent, L.F. Miller, A. Olsen and W. Snyder, "Development of a Downhole Logging System," 

Proceedings of the Health Physics Society 1993 Annual Meeting (July 1993) 

Y. Feng, K.S. Brown, W.H. Casson, G.T. Mei, L.F. Miller and M. Thein, Determination of Neutron Dose 

from Criticality Accidents with Bioassays for Sodium-24 in Blood and Phosphorus-32 in Hair, Oak Ridge 

National Laboratory, ORNL/TM-12028, National Technical Information Service Springfield, VA (June 

1993) 


L. F. Miller, Y. Feng, W. Casson and G. Mei, "Accident Neutron Dosimetry Using Blood and Hair," 

Transactions of the American Nuclear Society (June 1992) 

L. F. Miller, F. Algutifan and R. E. Uhrig, "An Application of Neural Networks and Artificial Intelligence 

19

for IN-Core Fuel Management," Transactions of the American Nuclear Society (November 1992) 

R. T. Wood, L. F. Miller and R. B. Perez, "Application of a Surveillance and Diagnostic Methodology 

Using Neutron Noise from a Pressurized Water Reactor," Nuclear Safety Vol 33 No 1 (January-March 

1992) 


L. F. Miller and G. T. Smith, "Evaluation of Neural Networks for Identification of Parameters in 

Mathematical Models," Transactions of the American Nuclear Society, Vol 63 (June 1991) 

L. F. Miller, "An Evaluation of Neural Networks for Identification of System Parameters in reactor Noise 

Signals," A Symposium on Nuclear Reactor Surveillance and Diagnostics, May 19-24, 1991, Gatlinburg, 

Tennessee (May 1991) 

L. F. Miller, Y. Feng, W. Casson, M. Thein and G. Mei, "Determination of Neutron Dose from Criticality 

Accidents with Bioassays for Na-24 and P-32," Third Conference on Radiation Protection and Dosimetry, 

Orlando, Florida, October 21-24, 1991 (October 1991) 


L.F. Miller, J.A. Thie, G.T. Smith and Y. Wu, "Positron Emission Perfusion Studies" Transactions of the 

American Nuclear Society, Vol. 61 (June 1990). 

L.F. Miller, G.T. Smith, Y. Wu and R.E. Uhrig, "Evaluation of Neural Networks for Parameter 

Identification from Positron Emission Tomography Studies," Transactions of the American Nuclear 

Society, Vol. 62 (Nov. 1990). 

G.T. Smith, Y. Wu and L.F. Miller, "Quantification of Myocardial Blood Flow with Dynamic Positron 

Emission Tomography," Transactions of the American Nuclear Society, Vol. 62 (Nov. 1990). 

L.F. Miller, C.A. Baldwin, F. W. Stallman, and F.B. Kam, Neutron Exposure Parameters for the 

Metallurgical Test Specimens in the Sixth Heavy-Section Steel Irradiation Series, NUREG/CR-5409, 

ORNL/TM-11267 (May 1990). 

Y. Feng, L. F. Miller and M. Thein, "Determining Accident Neutron Dose Using Hair and Blood," 36th 

Annual Conference on Bioassay, Analytical & Environmental Radiochemistry, Oak Ridge Associated 

Universities, Oak Ridge, Tennessee (Oct. 1990). 


R. E. Uhrig and L. F. Miller, "Use of Neural Networks for In-Core Fuel Management," Transactions of the 

American Nuclear Society, (June 1989). 

H. M. Hashemian, K. Peterson, M. Hashemian, D. Beverly, L. F. Miller, J. Ginrich, R. Fain and S. 

Johnson, "In-Situ Response Time Testing of Thermocouples," ISA 35th International Instrument 

Symposium, Orlando, Florida, (May 1989). 

20

L. F. Miller, "Characterization of Radioactive Waste," Sixteenth Annual WATTec Interdisciplinary 

Technical Conference and Exhibition, Knoxville, Tennessee, February 14-17, (February 1989). INVITED 

H. M. Hashemian, K. Peterson, L. F. Miller, J. A. Thie, R. E. Fain, 

M. Hashemian, D. D. Beverly, B. R. Upadhyaya and J. J. Gingrich, "Application of Noise Analysis for 

Response Time Testing of Pressure Sensors in Nuclear Power Plants," Seventh Power Plant Dynamics, 

Control and Testing Symposium, May 15-17, 1989, Knoxville, Tennessee. 

L. F. Miller and H. M. Hashemian, "In-Situ Response Time Testing of Force Balance Pressure 

Transmitters in Nuclear Power Plants," Seventh Power Plant Dynamics, Control and Testing Symposium, 

May 15-17, 1989, Knoxville, Tennessee 


L. F. Miller, C. A. Baldwin, F. W. Stallman and F. B. K. Kam, Neutron Exposure Parameters for the 

Metallurgical Test Specimens in the Fifth Heavy Section Steel Technology Irradiation Series Capsules, 

NUREG/CR-5019, ORNL/TM-10582, U.S. Nuclear Regulatory Commission, Washington, D.C. (March 

1988) 


L. F. Miller, E. S. Stetar, J. H. Coleman, A. Payne, J. Hoffelt and D. J. Auslander, "Monitoring of 

Radionuclide Migration and Exposure Rates from the American Nuclear Corporation Plant Site," 

Proceedings of the Oak Ridge Model Conference, Oct. 14-16, 1987, Martin Marietta Energy Systems, Inc., 

Oak Ridge, TN (1987) 

L. F. Miller, "LWR Pressure Vessel Surveillance Dosimetry Improvement Program: Sections 1.0, 1.1, 1.2, 

1.3, 3.0, 3.1," PSF Physics-Dosimetry Program, NUREG/CR-3320, Vol. 3, U.S. Nuclear Regulatory 

Commission (October 1987) 

L. F. Miller, "Description of the Experimental Facility - Summary," LWR Pressure Vessel Surveillance 

Dosimetry Improvement Program: PSF Physics-Dosimetry Program, NUREG/CR-3320, Vol 3, HEDL- 

TME 87-3, Section 1.0, U.S. Nuclear Regulatory Commission, Washington, D.C., (October 1987). 

L.F. Miller, "Physical Description of the SSC, SCVC, and SVBC," LWR Pressure Vessel Surveillance 

Dosimetry Improvement Program: PSF Physics-Dosimetry Program, NUREG/CR-3320, Vol. 3, HEDL- 

TME 87-3, Section 1.1, U.S. Nuclear Regulatory Commission, Washington, D.C., (October 1987). 

L. F. Miller, "Calculated Core Power Source," LWR Pressure Vessel Surveillance Dosimetry Improvement 

Program: PSF Physics-Dosimetry Program, NUREG/CR-3320, Vol. 3, HEDL-TME 87-3, Section 1.3, 

U.S. Nuclear Regulatory Commission, Washington, D.C., (October 1987). 

L. F. Miller, "Transport Calculation Results - Summary," LWR Pressure Vessel Surveillance Dosimetry 

Improvement Program: PSF Physics Dosimetry Program, NUREG/CR-3320, Vol. 3, HEDL-TEM 87-3, 

Section 3.0, U.S. Nuclear Regulatory Commission, Washington, D.C., (October 1987). 

L. F. Miller, "ORNL Analysis," LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PSF 

21

Physics-Dosimetry Program, NUREG/CR-3320, Vol. 3, HEDL-TME 87-3, Section 3.1, U.S. Nuclear 

Regulatory Commission, Washington, D.C., (October, 1987). 

L. F. Miller, "Physical Description - SSC, SPVC, and SVBC Experiments," LWR Pressure Vessel 

Surveillance Dosimetry Improvement Program: PSF Metallurgy Program, NUREG/CR-3320, Vol. 4, 

HEDL-TME 87-4, Section 1.1, U.S. Nuclear Regulatory Commission, Washington, D.C., (November 

1987). 

L. F. Miller, "Temperature Control - SSC and SPVC Experiments," LWR Pressure Vessel Surveillance 

Dosimetry Improvement Program: PSF Metallurgy Program, NUREG/CR-3320, Vol.4, HEDL-TME 87-4, 

Section 1.3, U.S. Nuclear Regulatory Commission, Washington, D.C., (November, 1987). 


L. F. Miller and M. L. Williams, Computational Methodology for the Oak Ridge Research Reactor (ORR) 

and Bulk Shielding Reactor (BSR): Cross-Section Generation and Validation, Volume I, NUREG/CR- 

3064, Vol. 1. ORNL/TM-9968/V1, U.S. Nuclear Regulatory Commission, Washington, D.C. (March 

1986) 

M. L. Williams and L. F. Miller, Computational Methodology for the Oak Ridge Research Reactor (ORR) 

and Bulk Shielding Reactor (BSR): The VICTORR Input Processing Code for the BOLD VENTURE 

System, Volume II, NUREG/CR-3064, Vol. 2, ORNL/TM-9968/V2, U.S. Nuclear Regulatory 

Commission, Washington, D.C. (April 1986) 

L. F. Miller and R. L. Shepard, Analysis of Loop Current Step Response Data Obtained from In-Situ Tests 

of Temperature Detectors, ORNL/TM-10087, Oak Ridge National Laboratory, Oak Ridge, Tennessee 

(May 1986) 

F. B. K. Kam, F. W. Stallman, L. F. Miller, M. L. Williams, and R. E. Maerker, "Program 

Documentation," LWR Pressure Vessel Surveillance Dosimetry Improvement Program 1985 Annual 

Report October 1984 - September 1985, NUREG/CR-4307, Vol. 1, HEDL-TME 85-14, U.S. Nuclear 

Regulatory Commission, Washington, D.C., (January 1986). 

M. L. Gordon and L. F. Miller, "Response Time of a Continuous Air Monitor to a Step Change in Leak 

Rate," TVA DNE Calculation, SQN ATS 3-054 (1986) 

L. F. Miller and F. B. K. Kam, "Sections 1.0, 1.1, 1.2 and 2.1," PSF Experiments Summary and Blind Test 

Results, NUREG/CR-3320, Vol. 1, U.S. Nuclear Regulatory Commission, National Technical Information 

Service (June 1986) 

L. F. Miller, G. L. Guthrie, and E. P. Lippencott, "Physical Description of the SSC, SPVC, and SVBC - 

Summary," LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PSF Experiments 

Summary and Blind Test Results, NUREG-CR-3320, Vol. I, HEDL-TME 86-8, Section 1.1. U.S Nuclear 

Regulatory Commission, Washington, D.C., (July 1986). 

L. F. Miller, "Temperature Control of SSC and SPVC - Summary," LWR Pressure Vessel Surveillance 

Dosimetry Improvement Program: PSF Experiments Summary and Blind Test Results, NUREG/CR-3320, 

22

Vol. 1, HEDL-TME 86-8, Section 1.2, U.S. Nuclear Regulatory Commission, Washington, D.C., (July 

1986). 

L. F. Miller, "ORNL Transport Analysis," LWR Pressure Surveillance Dosimetry Improvement Program: 

PSF Experiments Summary and Blind Test Results, NUREG/CR-3320, Vol. 1, HEDL-TME 86-8, Section 

2.1, U.S. Nuclear Regulatory Commission, Washington, D.C., July 1986. 

L. F. Miller and F. B. K. Kam, Sect. A.6, " Irradiation History and Neutron Source Distributions for the 

SDMF Experiments, " LWR Pressure Vessel Surveillance Dosimetry Improvement Program, 1985 Annual 

Report, NUREG/CR-4307, HEDL-TME 85-14, Vol. 1, U.S. Nuclear Regulatory Commission, 

Washington, D.C. (January 1986) 


G. E. Ragan, T. W. Kerlin and L. F. Miller, "Dynamic Testing of Pressure Sensing Lines in Nuclear Power 

Plants," Transactions American Nuclear Society, Vol 50 (November 1985) 

L. F. Miller and R. W. Hobbs, "Data Acquisition and Control System for the K1C-HSST Experiments at the 

ORR," Proc. of the 5th ASTM-EURATOM Symposium on Reactor Dosimetry, September 24-28, 1984, 

Geesthacht, FRG (1985) 

L. F. Miller and R. W. Hobbs, Data Acquisition and Control of the HSST Serves V Irradiation Experiment 

at the ORR, NUREG/CR-3872, ORNL/TM-9253, U.S. Nuclear Regulatory Commission, Washington, 

D.C. (March 1985) 

M. E. Buchanan, L. F. Miller, J. A. Thie, T. W. Kerlin, G. E. Ragan and J. March-Leuba, Measurement of 

Response Time and Detection of Degradation in Pressure Sensor/Sensing Line Systems, NUREG/CR- 

4256, ORNL/TM-9574, U. S. Nuclear Regulatory Commission, Washington, D.C. (September 1985) 

M. E. Buchanan, L. F. Miller, J. A. Thie, T. W. Kerlin, G. Ragan and J. March-Leuba, Measurement of 

Response Time and Detection of Degradation in Pressure Sensor/Sensing-Line Systems," Nuclear 

Engineering and Design 89, NED 755G, North-Holland Amsterdam (1985) 

L. F. Miller, "Source Terms for the Design and Analysis of Shielding Relative to Storage and Handling, 

Decontamination and Maintenance Facilities," TV-62833A, Department of Nuclear Engineering, The 

University of Tennessee (July 1985) 

L. F. Miller, "Sections 1.0, 1.1, 5.0, 5.1.2," LWR Pressure Vessel Surveillance Dosimetry Improvement 

Program: PCA Dosimetry in Support of the PSF Physics-Dosimetry-Metallurgy Experiments, 

NUREG/CR-3318 (Revision), U.S. Nuclear Regulatory Commission, Washington, D.C. (1985) 

L. F. Miller, "Sections 1.0, 1.1, 1.2, 4.0, 4.1," LWR Pressure Vessel Surveillance Dosimetry Improvement 

Program: PSF Startup Experiment, NUREG/CR-3320, Vol.2, U.S. Nuclear Regulatory Commission, 

Washington, D.C. (1985) 

L. F. Miller, "Sections 1.0, 1.1, 1.2, 1.3, 4.1, 4.5," LWR Pressure Vessel Surveillance Dosimetry 

Improvement Program: Service Laboratory Procedures Verification and Surveillance Capsule 

23

Perturbations, NUREG/CR-3321, U.S. Nuclear Regulatory Commission, Washington, D.C. (1985) 


A. J. Soares, L. F. Miller and T. W. Kerlin, "Response Time Testing of Force Balance Pressure 

Transmitters," Proc. of the 31st Remote Systems Technology Division, American Nuclear Society, 

Chicago, Illinois (March 1984) 

M. E. Buchanan, L. F. Miller, J. A. Thie, T. W. Kerlin, G. E. Ragan and J. March, "Measurement of 

Response Time and Detection for Degradation in Pressure Sensor/Sensing Line Systems," Proc. of the 12th 

Water Reactor Safety Research Information Meeting, U.S. Nuclear Regulatory Commission, Washington, 

D.C. (October 1984) 

C. A. Baldwin, F. B. K. Kam, L. F. Miller and F. W. Stallman, "Calculations and Measurements for the 

PCA 4/12 and 4/12 SCC Configurations, " LWR Pressure Vessel Surveillance Dosimetry Improvement 

Program: PCA Experiments, Blind Test and Physics-Dosimetry Support for the PSF Experiment, 

NUREG/CR-3318, HEDL-TME 84-1, U.S. Nuclear Regulatory Commission, Washington, D.C., pp. 5.1-6 

through 5.1.-12 (September 1984) 

C. A. Baldwin, L. F. Miller and F. B. K. Kam, "Neutronics Calculations for the Pool Critical Assembly - 

4/12 SSC and 4/12 Configuration," LWR Pressure Vessel Surveillance Dosimetry Improvement Program 

Semiannual Progress Report October 1983-March 1984, NUREG/CR-3746, Vol. 1, HEDL-TME 84-20, 

U.S. Nuclear Regulatory Commission, Washington, D.C., pp. ORNL 71-99 (November 1984) 


L. F. Miller, J. T. Mihalczo, E. G. Bailiff, N. D. Woody and G. D. Gardner, "Nuclear Engineering 

Laboratory Self-Regulated Power Oscillations at the Health Physics Research Reactor," Transactions of the 

American Nuclear Society, Vol. 44 (June 1983) 

C. A. Baldwin, L. F. Miller, F. B. K. Kam and G. Minsart, "Neutronic Calculations for the Pool Critical 

Assembly (PCA) 4/12 and 4/12 + SSC Configurations," LWR Pressure Vessel Surveillance Dosimetry 

Improvement Program Quarterly Progress Report October 1982-December 1982, NUREG/CR-2805, Vol. 

4, HEDL-TME 82-21, U.S. Nuclear Regulatory Commission, Washington, D.C., pp. ORNL 1-14 (July 

1983) 

F. B. K. Kam, F. W. Stallman, L. F. Miller, R. E. Maerker, M. L. Williams, R. D. Cheverton and C. A. 

Baldwin, "Light Water Reactor Pressure Vessel (LWR-PV) Benchmark Facilities (PCA, ORR-PSF, ORR- 

SDMF) at ORNL," LWR Pressure Vessel Surveillance Dosimetry Improvement Program, Quarterly 

Progress Report January 1982-March 1982, NUREG/CR-2805, Vol. 2, HEDL-TME 82-18, U. S. Nuclear 

Regulatory Commission, Washington, D. C., pp. ORNL 1-38 (January 1983) 


A. J. Soares, T. W. Kerlin and L. F. Miller, "Dynamic Analysis of a Foxboro Pressure Transducer," 

Transactions of the American Nuclear Society, Vol. 43 (November 1982) 

24

L. F. Miller, "Feasibility Study for the Removal of Intermediate Half-Life Isotopes from Low Level 

Radioactive Waste," TVA/OP/EDT-82/8 (May 1982) 

L. F. Miller, "Control of the ORR-PSF Pressure Vessel Surveillance Irradiation Experiment Temperature," 

Proc. of the Fourth ASTM-EURATOM Symposium on Reactor Dosimetry, NUREG/CR-0029, U.S. 

Nuclear Regulatory Commission, Washington, D.C. (July 1982) 

F. B. K. Kam, F. W. Stallman and L. F. Miller, "Light Water Reactor Pressure Vessel (LWR-PV) 

Benchmark Facilities (PCA, ORR-PSF, ORR-SDMF) at ORNL," and "ASTM Standards for Surveillance 

of Nuclear Reactor Pressure Vessels," LWR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly 

Progress Report October 1981-December 1981, NUREG/CR-2345, Vol. 4, HEDL-TME 81-36, U.S. 

Nuclear Regulatory Commission, Washington, D.C. (1982) 

F. B. K. Kam, F. W. Stallman and L. F. Miller, "Light Water Reactor Pressure Vessel (LWR-PV) 

Benchmark Facilities (PCA, ORR-PSF, ORR-SDMF) at ORNL," and "ASTM Standards for Surveillance 

of Nuclear Reactor Pressure Vessels," LWR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly 

Progress Report April 1981-June 1981, NUREG/CR-2345, Vol.2, HEDL-TME 81-34, U.S. Nuclear 

Regulatory Commission, Washington, D.C. (December 1982) 


L. F. Miller, Analysis of Temperature Data from the ORR-PSF Irradiation Experiment: Methodology and 

Computer Software, NUREG/CR-2273, U.S. Nuclear Regulatory Commission, Washington, D.C. 


J. O. Johnson, L. F. Miller and F. B. K. Kam, Neutronics Model of the Bulk Shielding Reactor (BSR): 

Validation by Comparison of Calculations with the Experimental Measurements, ORNL/TM-7128, Oak 

Ridge National Laboratory, Oak Ridge, Tennessee (May 1981) 

L. F. Miller, C. A. Baldwin, R. E. Maerker and J. J. Wagschal, "Neutron Field Characterization Transport 

Calculations," LWR Vessel Irradiation Quarterly Progress Report April-June 1979, NUREG/CR-1240, 

Vol. II, U.S. Nuclear Regulatory Commission, Washington, D.C. (January 1981). 

L. F. Miller, Contributor, LWR Pressure Vessel Surveillance Dosimetry Improvement Program 1980 

Annual Report, NUREG/CR-1747, U.S. Nuclear Regulatory Commission, Washington, D.C. (April 1981) 

L. F. Miller, F. B. K. Kam, C. A. Baldwin and S. H. Merriman, "Benchmark Fields," LWR Pressure 

Vessel Irradiation Surveillance Dosimetry Quarterly Progress Report April-June 1980, NUREG/CR-1241, 

Vol. II, U.S. Nuclear Regulatory Commission, Washington, D.C. (May 1981) 

L. F. Miller and F. B. K. Kam, "6.0 Neutronic Calculation Methods" LWR Pressure Vessel Surveillance 

Dosimetry Program: PCA Experiments and Blind Test, NUREG/CR-1861, U.S. Nuclear Regulatory 

Commission, Washington, D.C. (July 1981) 

F. W. Stallman et al., "Core Power Measurements and Calculations, and Buckling Data," LWR Pressure 

Vessel Surveillance Dosimetry Improvement Program, PCA Experiments and Blind Test, NUREG/CR- 

1861, HEDL-TME 80-87, Section 1.2, U.S. Nuclear Regulatory Commission, Washington, D.C. (July, 

25

1981). 

F. B. K. Kam, F. W. Stallman, and L. F. Miller, "Light Water Reactor Pressure Vessel (LWR-PV) 

Benchmark Facilities (PCA, ORR-PSF, ORR-SDMF) at ORNL," LWR Pressure Vessel Irradiation 

Surveillance Progress Report January-March 1981, NUREG/CR-2345, Vol. I, HEDL-TME 81-33, U.S. 

Nuclear Regulatory Commission, Washington, D.C., (October 1981). 

F. B. K. Kam, L. F. Miller and F. W. Stallman, "Light Water Reactor Pressure Vessel Benchmark 

Facilities at ORNL" and "ASTM Standards for Surveillance of Nuclear Reactor Pressure Vessels," LWR 

Pressure Vessel Irradiation Surveillance Dosimetry Quarterly Progress Report January 1981-March 1981, 

NUREG/CR-2345, Vol. I, U.S. Nuclear Regulatory Commission, Washington, D.C. (October 1981) 

F. B. K. Kam, L. F. Miller, F. W. Stallman, C. A. Baldwin, R. E. Maerker and A. Fabry, "Light Water 

Reactor Pressure Vessel Benchmark Facilities at ORNL" and "ASTM Standards for Surveillance of 

Nuclear Reactor Pressure Vessels, "LWR Pressure Vessel Irradiation Surveillance Dosimetry Quarterly 

Progress Report October-December 1980, NUREG/CR-1241, Vol. 4, U.S. Nuclear Regulatory 

Commission, Washington, D.C. (November 1981) 


L. F. Miller and C. A. Baldwin, "Neutronics Calculations for the Bulk Shielding Reactor Heavy Section 

Steel Technology Irradiation Experiment," ORNL/CF-80-45, Oak Ridge National Laboratory, Oak Ridge, 

Tennessee (February 1980) 

T. W. Kerlin, L. F. Miller, H. M. Hashemian, W. P. Poore, M. Skorska, B. R. Upadhyaya, P. Cormault and 

J. P. Jacquot, Temperature Sensor Response Characterization, EPRI NP-1486, Electric Power Research 

Institute, Palo Alto, California (August 1980) 

W. N. McElroy et al., "LWR Pressure Vessel Surveillance Dosimetry Improvement Program," Proc. of the 

Third ASTM-EURATOM Symposium on Reactor Dosimetry, EUR 6813, October 1-5, 1979, Ispra, Italy, 

pp. 334-385, (1980). 

F. B. K. Kam, A. Fabry, F. W. Stallman, G. Minsart, E. D. McGarry, L. F. Miller, J. H. Swanks and W. N. 

McElroy, "The Core Power of the Pool Critical Assembly Light Water Pressure Benchmark," Proc. of the 

3rd ASTM-EURATOM Symposium on Reactor Dosimetry, EUR 6813, Ispra, Italy, pp. 980-988 (1980) 

L. F. Miller, C. A. Baldwin and J. O. Johnson, Neutronics Calculations for the Bulk Shielding Reactor 

Heavy Section Steel Technology Irradiation Experiment, ORNL/TM-8045, Oak Ridge National 

Laboratory, Oak Ridge, Tennessee (February 1980) 

L. F. Miller, A Computerized Process Control System for the ORR-PSF Irradiation Experiment, Part 2: 

Mathematical Basis and Computer Implementation of the Temperature Control Algorithm, NUREG/CR- 

1710, Vol.2, ORNL/NUREG/TM-405/P2, U.S. Nuclear Regulatory Commission, Washington, D.C. 


L. F. Miller, F. B. K. Kam and L. P. Pugh, "Benchmark Fields," LWR Pressure Vessel Irradiation 

Surveillance Dosimetry Quarterly Progress Report January-March 1980, NUREG/CR-1241 Vol. I, U.S. 

Nuclear Regulatory Commission, Washington, D.C. (December 1980) 

26

L. F. Miller, C. A. Baldwin, R. E. Maerker, F. B. K. Kam and J. J. Wagschal, "Neutron Field 

Characterization - Transport Calculations," LWR Pressure Vessel Irradiation Surveillance Dosimetry 

Quarterly Progress Report January-March 1979, NUREG/CR-1240, Vol. I, U.S. Nuclear Regulatory 

Commission, Washington, D.C. (December 1980) 

L. F. Miller, C. A. Baldwin, R. E. Maerker, G. Minsart and J. J. Wagschal, "Neutron Field 


Quarterly Progress Report July-September 1979, NUREG/CR-1240, Vol. III, U.S. Nuclear Regulatory 

Commission, Washington, D.C. (December 1980) 

L. F. Miller, C. A. Baldwin, R. E. Maerker, J. J. Wagschal and G. Minsart, "Neutron Field 


Quarterly Progress Report January-March 1980, NUREG/CR-1241, Vol. I, HEDL-TME 80-4, U.S. 

Nuclear Regulatory Commission, Washington, December 1980. 

L. F. Miller et al., "Neutron Field Characterization - Transport Calculations," LWR Pressure Vessel 

Irradiation Surveillance Dosimetry Quarterly Progress Report October-December 1979, NUREG/CR-1240, 

Vol. IV, HEDL-TME 80-3, U.S. Nuclear Regulatory Commission, Washington, D.C., (December 1980). 


L. F. Miller and F. B. K. Kam, "Design Support Calculations," LWR Pressure Vessel Irradiation 

Surveillance Dosimetry Quarterly Progress Report April-June 1978, NUREG/CR-0550, HEDL-TME 78-7, 

U.S. Nuclear Regulatory Commission, Washington, June 1979. 

L. F. Miller, J. O. Johnson and F. B. K. Kam, "Verification of Shielding Requirements for ILW 

Improvements," ORNL/CF-78/341, Oak Ridge National Laboratory, Oak Ridge, Tennessee (May 1979) 


L. F. Miller, R. G. Cochran and J. W. Howze, "Output Feedback Stabilization by Minimization of Spectral 

Radius Functional." Intl. J. Control, Vol. 27, No. 3, pp. 455-462 (1978) 

T. W. Kerlin, L. F. Miller and H. M. Hashemian, "In-Situ Response Time Testing of Platinum Resistance 

Thermometers," ISA Transactions, Vol. 17, No.4 (1978) 

T. W. Kerlin, L. F. Miller, H. M. Hashemian and W. P. Poore, In-Situ Response Time Testing of Platinum 

Resistance Thermometers, EPRI NP-834, Electric Power Research Institute, Palo Alto, California (July 

1978) 

L. F. Miller and J. O. Johnson, "Neutron Field Characterization-Transport Methods, "LWR Pressure 

Vessel Irradiation Surveillance Dosimetry Quarterly Progress Report, July-September 1978, NUREG/CR- 

0551, HEDL-TME 78-8, U.S. Nuclear Regulatory Commission, Washington, D.C., pp. ORNL 3-52 

(December 1978) 


27

T. W. Kerlin, L. F. Miller and H. M. Hashemian, "In-Situ Response Time Testing of Temperature Sensors, 

" Transactions of the American Nuclear Society (1977) 

L. F. Miller, R. G. Cochran and J. W. Howze, "Output Feedback Stabilization Using a Global Method for 

Solving Polynomial Inequalities," IEEE Transactions on Automatic Control, AC-22 (February 1977) 

L. F. Miller, R. G. Cochran and J. W. Howze, "Nuclear Reactor Control System Design with Sensor 

Failure," Nuclear Technology, Vol.36, No. 1 (November 1977) 

L. F. Miller, "Analysis of Loop Current Step Response Data Obtained From In-Situ Tests of Temperature 

Detectors," ORNL/CF-77/467, Oak Ridge National Laboratory, Oak Ridge, Tennessee (November 1977) 


Laurence Frederick Miller, "Nuclear Reactor Control System Design with Sensor Failure," Texas A&M 

University (August 1976), Dissertation 

Prior to 1976 

L. F. Miller, "Effects of Radiation Quality on the Radiolysis of Water (SR-66)," Kansas Engineering 

Experiment Station (1966), Master's Thesis 

R. E. Faw and L. F. Miller, "Charged Particle Slowing Down Spectra for Fast Neutron Irradiation of 

Water," Transactions of the American Nuclear Society (1965) 

R. K. Disney, L. F. Miller and J. M. Ravets, "Power Flattening for Thermionic Reactors," Transactions of 

the American Nuclear Society (1967) 

R. E. Faw and L. F. Miller, "Track Effects in Radiation Induced Chemical Reactions," Journal of the 

AIChE (1966) 

H. R. Leribaux and Laurence F. Miller, "Structure of the Liquid Alkali Metals by an Optimized Iterative 

Solution of the Percus-Yevick Equations," J. Chem. Phys., Vol. 61, No.8 (October 1974) 

GRADUATE STUDENTS DIRECTED AT THE MASTERS LEVEL. Single Entries Designate Thesis 

Titles and Multiple Listings Identify Engineering Practice Report Titles 

Jeffrey O. Johnson (March 1980) 

1) Neutron Model Evaluation for LWR Pressure Vessel Irradiation Surveillance Improvement Program 

(published as ORNL/CF-8117, January 1981) 

2) Neutron Model of BSR: Validation by Comparison with Experimental Measurements (published as 

ORNL/TM-7128, May 1981) 

Charles A. Baldwin (March 1984) 

1) Two and Three Dimensional Diffusion Theory Calculations for the Pool Critical Assembly Pressure 

Vessel Wall Benchmark Facility 

2) Two Dimensional Discrete Ordinate Transport Theory Calculations for the Pool Critical Assembly 

28

Pressure Vessel Wall Benchmark Facility 

3) Neutron Spectral Characterization Calculations for the Fourth Nuclear Regulatory Commision Heavy 

Section Steel Technology 1T-CT Irradiation Experiment 

Randy W. Hobbs (June 1985) 

1) Flux Measurements: ORR Core Configuration 164-AX12 

2) ORR Core Re-Configuration Measurements to Increase the Fast Neutron Flux in the Magnetic Fusion 

Energy (MFE) Experiments 

3) Data Acquisition and Control Systems for the K1c-HSST Experiments at the ORR 

J. A. Buczek (June, 1988) 

1) A Fuel Utilization Plan for TVA's Watts Bar Nuclear Plant Unit 1 

2) A Benchmark of the CASMO-2/PDQ-7 Computer Codes Using Critical Experiments 

3) PLOTSTP-A Computerized Processor of STP Input 

J.L. King (August 1988) 

1) Determination of a Doppler Correction Factor to be Applied to CASMO's Cross Section Library 

2) PRESTO-II: A Large Computer Code Application of the ADGEN/EXAP System 

S.B. Thomas (Dec. 1989) 

Verification of a Three-Dimensional Reactor Core Simulator Using QUAD-CITIES Data 

Louise Buker (Dec. 1990) 

Sensitivity Comparison from Measurements of Various High Purity Germanium Spectrometers 

Yuexin Wu (Dec. 1990) 

Measurement of Regional Myocardial Blood Flow by a Compartment Modeling Method 

David Goff (May 1991) 

Surface Radiological Investigations at a Low-Level Liquid Waste Burial Trench 

Ying Feng (May 1991) 

Determination of Neutron Dose from Criticality Accident with Bioassays for Blood- 24 Na and Hair 32 P 

Jonathan Snapp (Dec. 1992) 

Development of a Neutron Area Monitor and Characterization System 

Mark Buckner (Dec. 1992) 

Evaluation of Bubble Detector Response in Reference Fields 

F. Algutifan (Dec. 1992) 

An Application of Artificial Intelligence for In-Core Reactor Fuel Management 

Robert Coleman (May 1993) 

Evaluation of Survey Instruments for Low Energy Beta Sources 

Janna Hammonds (Aug. 1993) 

Quantitative Uncertainty Analysis for the Human Fish Ingestion Pathway: Select Radionuclide and 

29

Chemical Contaminants in the Clinch River/Watts Bar Reservoir System 

Richard Raver (Aug. 1993) 

Determination of Detector Response to Beta/Gamma Sources Using the ITS Monte Carlo Code 

David King (Dec. 1993) 

Correlation of Radon Measurements in Houses with Geological Parameters 

Michelle Johnson (Dec. 1993) 

Calibration and Characterization of Research X-Ray Unit 

Bryan Johnson (Dec. 1993) 

Radiological Assessment of the 903 Pad, Mound, East Trenches, and Off-Site Areas at the Rocky Flats 

Plant 

Syed Maswood (Dec. 1993) 

1) An Alternative Calibration Technique for High Purity Germanium Detectors-Point Source Evaluation 

2) Non Conventional Calibration of Germanium Detector for Cylindrical Geometry using Nominal 

Detector Specifications 

3) Programmable Signal Processing Electronics and Its Benefits in Nuclear Counting Systems 

Mark Smith (Dec. 1993) 

1) Development of Radionuclide Concentration-Based Waste Acceptance Criteria for a Low-Level 

Radioactive Waste Disposal Facility and Some Considerations in Their Implementation 

2) Strategy for Applying Nondestructive Assay and Nondestructive Examination Technology to 

Radioactive Waste Management on the Oak Ridge Reservation 

3) Solid Waste Storage Area 6 Performance Assessment Inventory Verification Study 

Elizabeth King Algutifan (May 1994) 

Assessment of Off-Site Radiological Hazards at the Oak Ridge K-25 Site: An Emergency Preparedness 

Perspective 

Travis Shaw Kroodsma (Aug 1994) 

Radiation Dose Assessment for Plutonium Contamination at Area 13 of the Nevada Test Site Using 

Nevada Applied Ecology Group Data and the RESRAD Code 

David Wayne Burkett (Aug. 1994) 

Evaluation of Two Procedures for Assaying Uranium in Soil 

Robert Christopher Jones (Aug. 1994) 

Development and Validation of Positron Emission Tomography methods for Determining Arterial Input 

Functions 

Lisa Rene Vickers (Aug. 1994) 

The Prediction Equations of the Male and Female Chest Wall Thickness for Measuring Actinides within 

the Lungs Using HPGe Detectors 

Hari N. Banerjee (Dec. 1994) 

30

1) Decontamination of Soil at Sites Under the Formerly Utilized Site Remediation Program 

2) Overview of Radioactive Waste management with Visual Aid Supplements 

3) Patlak Plots Using the BASIC Computer Language for use With Personal Computers 

Jason Brook Miller (Dec. 1994) 

Development of a Field Method for the Detection of Technetium-99 in Soil 

Eugenia Beth Lee (Dec. 1994) 

Accident Dosimetry Using Panasonic Dosimeters 

Alan Scott Icenhour (May 1995) 

Analysis of Source Term Modeling for Low-Level Radioactive Waste Performance Assessments 

Richard Duane Korynta (May 1995) 

Analysis of a Radiological Box Monitor for Source Segregation 

David F. French (May 1995) 

Assessment of a Continuous Air Monitor for the Detection of Airborne Transuranics 

Edward Bolling Ripley (May 1995) 

Modification and Assessment of a Portable Alpha Scintillation Detector 

Brian Spencer Cowell (Aug. 1995) 

Assessment of Actinide Recycle on High Level Waste Disposal 

Nithyananda G. Narayana (Aug. 1995) 

Neural Networks for Parameter Identification in Compartment Models 

Joy Renee Russell (Aug. 1995) 

Radiation Absorbed Dose to the Embroy/Fetus from Nuclear Medicine Procedures 

Nancy Wakefield Richards (Aug. 1995) 

The Development of Models to Predict the In Vivo Background in Phoswich Lung Count Spectra 

Jeffery L. Brock (Dec. 1995) 

The Evaluation of Thermally Stimulated Exoelectron Emission Detectors and Electret Ionization Chambers 

for the Purpose of Measuring Tritium on Surfaces 

Duane Eugene White (Dec. 1995) 

A Radiological Assessment of the SLAPS and Ball Field FUSRAP Sites near the St. Louis Airport, St. 

Louis, Missouri 

Mark McHugh (Dec. 1995) 

Development of a Survey Method to Determine Radioactivity in Piping 

Kelly Lee Ausbrooks (May 1996) 

Non-Destructive Assay of Drum Packaged Radioactive Waste Utilizing Tomographic Gamma Scanning 

31

Cathy Jo Lewis (May 1996) 

Measurement of Neutron Dose Near an Accelerator Used for Radiation Therapy 

Bulent Aydogan (May 1996) 

Uncertainty Analysis for Absorbed Dose of a Brain Receptor Imaging Agent 

Lien Khanh Nguyen (May 1997) 

Characterization of ORNL Transuranic Waste from the Measurement of Fission and Activation Products 

Kelly M. Spencer (May 1997) 

Uncertainty Analysis of a Radiological Assessment of the Down-Town St. Louis FUSRAP Site 

Tom Byrne (August 1997) 

In Vitro Determination of Uptake and Biological Efficacy of Boronated Compounds for Neutron Capture 

Therapy in the Human Lung Cancer Line A549 

Dan Chase(May 1998) 

Determination of the Dose Rate from Naturally Occurring Radionuclides in Soil 

Don Marsh(May 1998) 

Design of a Solvent Extraction Process to Separate Plutonium and Neptunium 

Christina Beth Pomatto (December 1998) 

Modeling the Response of a Harshaw Albedo Neutron Dosimeter Using the Monte Carlo N-Particle 

Transport Code, MCNP. 

Brian Thomas (December 1998) 

Radiation Doses and Health Risks from Radionuclides Released into the Clinch River in Support of the 

Oak Ridge Dose Reconstruction Project 

Jennifer Kasten (May 1999) 

Project #1- “Radiolytic Hydrogen Gas Generation in a Storage/Shipping/Disposal Cask Containing Spent 

PWR Fuel” 

Project #2 – Evaluation of Parameters Relating Positron Emission Tomography Image Data to Sample 

Blood Data” 

Mohammad Khurram Khan (May 1999) 

Use of Positron Emission Tomography (PET) to Improve Radiation Dosimetry for Boron Neutron Capture 

Therapy (BNCT) 

John Keith Waggoner (August 1999) 

Neutron Shielding Effectiveness of Goethite High Density Concrete 

Field Test of the REM 500 TM Portable Neutron Survey Instrument 

Andrew Stephan (Dec. 1999) 

Characterization and Evaluation of a Micro Cantilever Radiation Detector 

William Jay Marshall (August 2001) 

32

Power Distribution Calculations in the High Flux Isotope Reactor for Various Control Blade Tantalum 

Loadings 

Cecil Craig Smith (Dec 2002) 

Salt Storage Canister Design for the Molten Salt Reactor Experiment 

Pneumatic Leak Tests of Half-Inch Lokring Couplings and Their Conversion to Liquid/Molten Salt 

Leakrate for the Molten Salt Reactor Experiment 

Brent Sumner (Dec 2002) 

Measurement of the Median Particle Size Diameter of Airborne Particles Collected Within Duratek’s 

Metal Melt Facility 

Robbie Alhakeem (Dec 2002) 

Determination of the Bremsstrahlung Spectra of a Clinical Linear Accelerator using a Simpson Iteration 

Technique 

Bob Gilliam (Dec 2003) 

ALARA Controls and the Radiological Lessons Learned During the Uranium Fuel Removal at the Molten 

Salt Reactor Project 

Henry Lynn (May 2004) 

Evaluation of Dose to Workers With and Without Respirators 

Carlos Corredor (Aug. 2004) 

Intercomparison of TLD Dose Measurements with Treatment Planning Software 

Mohammad Kasraie (May 2005) 

1) The use of 8-bit high-speed digitizers for displaying pulse shapes from scintillation detectors\ 

2) Establishing a live connection to The NC State Pulstar Reactor Control Displays Using an RTP link 

Joseph McConn (May 2006) 

Initial Design Evaluation of a Slab Core Lead-Bismuth Eutectic Reactor 

Gary Sweder (May 2006) 

Uncertainty Analysis of Several Advanced Fuel Cycles 

Kyle Klenihans (Dec 2006) 

Uncertainties Associated with Field Screening Measurements 

Jeff Preston (Dec 2006) 

Uncertainties Associated With Repository Heat Loads 

Chris Whitener (Aug 2007) 

Neutron Measurements and Spectrometry at Spent Fuel Casks 

Thomas Anderson (December 2007) 

Uncertainty Analysis of the Utilization and Implementation of Advanced Fuel Cycles to Control 

33

Plutonium Inventories 

Jia Hou (December 2007) 

Artificial Neural Network for Spectrum Unfolding Bonner Sphere Data 

Stephen Frederiksen (December 2007) 

Spatial Distribution of Induced Fission from the Pixilated Alpha Detector in a D-T Generator 

Matthew Humberstone (December 2007) 

Advanced Burner/Breeder Reactor Analysis of Isotope Production and Decay Heat for Varying 

Burnup and Changing Core Configurations 

Erika Bailey (May 2008) 

Radiological Scoping Survey of the Scotia Depot at Scotia, New York 

Julie Danzer (August 2008) 

Optically Stimulated Luminescence of Aluminum Oxide Crystals forRadiation Therapy Quality 

Assurance 

MatriXX for Quality Assurance Testing Following the TG51/TG40 Guidelines 

Stephan Janson (May 2009) 

Neutron and Gamma Scintillation Detector Characterization Protocol and Analysis 

Isotopic Decay Heat Analysis of Thorium Fueled Molten Salt Reactor and Gas-Cooled Reactor 

Alex Green (May 2010) 

Characterization of Detectors for the Transformational Scintillation Materials for Nuclear Threat 

Reduction Project 

Jeffrey Clark (August 2010) 

Updating the Cross-Section Library for the ORIGEN-ARP SCALE Module 

Nicholas Luciano (May 2012)(Completed requirements, 28 Nov 2011) 

Characterization of the Neutron Spectrum in the Spallation Neutron Source 

DOCTORAL STUDENTS DIRECTED 

Aiman Amir (Dec. 1992) 

Uncertainty Analysis of Neural Networks 

Ying Feng (Aug. 1995) 

Transport of Aquatic Contaminant and Assessment of Radioecological Exposure with Spatial and 

Temporal Effects 

Zhong Cao (Dec. 1997) 

34

New Methods for Neutron-Photon Pulse Shape Discrimination 

Emran Aziz Dawoud (Dec. 1998) 

The Multiple Convolution Integral Approach to Uncertainty Analysis in Fate and Transport Models used 

in Risk Assessment 

Loong Kwet Yong (Dec. 1998) 

Improvement of the Limit State Method for Uncertainty Analysis of Radionuclide Transport 

Richard Blaine Sparks (Dec. 1998) 

Automatic Identification of Organ/Tissue Regions in CT Image Data for the Implementation of Patient 

Specific Phantoms for Treatment Planning in Cancer Therapy 

Alan S. Icenhour (May 2000) 

Radiolytic Effects on Fluoride Impurities in a U3O8 Matrix 

Iulian Andrei Apostoaei (May 2001) 

Determination of the Uncertainties in Radiation Doses from Ingestion of 90 Sr 

Mohammad Khurram Khan (May 2002) 

Usu of 18 F-BPA PET Images and Image Registration to Enhance Radiation Treatment Planning for Boron 

Neutron Capture Therapy 

Ahmed Abdul-Rahim (May 2003) 

Determination of Cellular Level Kinetics of F-18 Tagged Phenelalanine and Evaluation of Infusion 

Protocols 

Andrew Stephan (December 2003) 

Monte Carol Simulation of Neutron Detectors 

Eric Abelquist (August 2008) 

Dose Modeling and Statistical Assessment of Hot Spots for Decommissioning Applications 

Jeff Preston (May 2010) 

Management Tool for Assessment of Alternative Fuel Cycles 

Martin Williamson (December 2010) 

Multivariate Optimization of Neutron Detectors Through Modeling 

Dustin Osborne (December 2011) 

Characterization of a Small Animal SPECT Platform for use in Preclinical Translational Research 

35

GRADUATE STUDENTS CURRENTLY DIRECTING AT THE MASTERS LEVEL. 

Matthew Urffer (Aug 2012) 

Design and Characterization of a Detector that Satisfies Department of Homeland Security Criteria 

DOCTORAL STUDENTS CURRENTLY DIRECTING 

Kevin Reynolds (December 2012) 

Fixed Source Sensitivity and Uncertainty Analysis for a Pulsed Critical Experiment 

Michael Howard (June 2013) 

Determination of Treatment Margins and Predictive Distributions for Prostrate Cancer Irradiation 

Robert Woolley (Aug 2012) 

System Studies of Fission-Fusion Hybrid Molten Salt Reactors (FFH-MSRs) 

36

TEACHING 

My primary teaching responsibilities have been reactor theory (NE-470 and NE-471) and nuclear 

engineering laboratory (NE-304 and NE-403). In addition, I have developed and taught the following new 

courses: 

1) Nuclear Fuel Management (NE-404) 

2) In-Core Fuel Management (NE-541) 

3) Management of Radioactive Materials (NE-542) 

4) Radiation Monitoring and Dose Assessment (NE-552). 

I have also developed the course content for a Master of Science level concentration of courses in 

Radiation Protection Engineering with collaboration from professionals at Oak Ridge National Laboratory 

and Oak Ridge Associated Universities. These courses are: 

1) Radiation Protection (NE-551) 

2) Nuclear Instrumentation (NE-550) 

3) Radiation Monitoring and Dose Assessment (NE-552). 

I regularly taught NE-552 and have developed the following new special topics courses faculty: 

1) Uncertainty Analysis (NE-597 and NE-621) 

2) Internal Dosimetry (NE-597 and NE-621) 

3) Medical Imaging (NE-597 and NE-621). 

The Internal Dosimetry and Medical Imaging courses have been taught with adjunct or associate faculty. 

The Radiation Protection courses and the Management of Radioactive Materials course have attracted a 

substantial number of students. About twenty new students have registered for the radiation protection 

program for several successive years, and the management of radioactive materials course was taught to 

about forty to fifty students each year from 1990 through 1995. The success of these courses has 

substantially benefited the overall enrollment of the Department of Nuclear Engineering. Specific teaching 

assignments are listed in Tables 1 and 2. 

37

Table 1. Undergraduate Teaching at The University of Tennessee 

Undergraduate Courses Taught by Quarter 

Academic Year Fall Winter Spring 

1976-1977 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

1977-1979 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

1978-1979 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

NE-4930 

1979-1980 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

NE-4930 

1980-1981 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

NE-4930 

1981-1982 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

NE-4930 

1982-1983 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

NE-4930 

1983-1984 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4930 

1984-1985 NE-4110 NE-4120 NE-4130 

NE-4210 NE-4220 NE-4230 

NE-4930 

1985-1986 NE-4110 NE-4120 NE-4130 

NE-4210 NE-5410 NE-5420 

1986-1987 NE-4110 NE-4120 NE-4130 

NE-4930 NE-4930 

1987-1988 NE-4110 NE-4120 NE-4130 

NE-4220 

38

Undergraduate Courses Taught by Semester 

Summer Fall Spring 

1988-1989 NE-404 NE-302 

NE-405 NE-304 

1989-1990 NE-401 

1990-1991 NE-403 

1991-1992 NE-470 

1992-1993 NE-470 

1993-1994 NE-470 

1994-1995 NE-470 

1995-1996 NE-470(UT) 

NE-470(OR) 

1996-1997 NE-470 

1997-1998 NE-471 

1998-1999 NE-471 

1999-2000 NE-301 NE-301 

2000-2001 NE-301 NE-304 

NE-301 (Video) 

2001-2002 NE-301 NE-301(Video) 

NE-301 (Video) NE-304 

NE-403 

2002-2003 NE-301(Video) NE-470 

NE-301distance NE-304 

NE-403 NE-470distance 

NE-470distance NE-distance 

2003-2004 NE-301 NE-304 

NE-403 NE-301distance 

NE-301distance NE-470distance 

NE-470distance NE-552 

2004-2005 NE-403 NE-304 

NE-470distance 

2005-2006 NE-403 NE-304 


2006-2007 NE-403 NE-304 


2007-2008 NE-403 NE-470distance 

2008-2009 NE-470distance 

2009-2010 

2010-2011 NE-404 

39

TABLE 2. Graduate Teaching at The University of Tennessee 

Graduate Courses Taught by Quarter 

Academic Year Fall Winter Spring 

1985-1986 NE-5410 NE-5420 

1987-1988 NE-5420 

Graduate Courses Taught by Semester 

Fall Spring Summer 

1988-1989 NE-542 

NE-550 (20%) 

1989-1990 NE-541 NE-542 NE-542 

NE-552 

1990-1991 NE-542(2 sections) NE-541 NE-542 

NE-552 

NE-621(Uncr. Anl.) 

1991-1992 NE-542(2 sections) NE-621(Uncr. Anl.) NE-542 

NE-552 

NE-597(Int. Dos.) 

1992-1993 NE-597(Med. Img.) NE-552 NE-542 

NE-542(2 sections) NE-597(Int. Dos.) 

1993-1994 NE-621(Uncr. Anl.) NE-552 NE-542 

NE-597(Uncr. Anl.) NE-597(Med. Img.) 

NE-542(2 sections) 

1994-1995 NE-542(2 sections) NE-552 NE-542 



1995-1996 NE-542 NE-552 NE-542 

NE-597(Med. Img.) 




1996-1997 NE-542 NE-541 NE-542 

NE-621(Med. Img.) NE-597(Unc.Anl) 

NE-621(Unc.Anl) 

NE-552 

40

Graduate Courses Taught by Semester(continued) 

Fall Spring Summer 

1997-1998 NE-542 NE-552 NE-542 

NE-597(Med.Img.) 


1998-1999 NE-542 NE-552 

NE-621 (Rad. Eff.) NE-550 

NE-597 (Rad. Bio.) 

1999-2000 NE-542 NE-552 

2000-2001 NE-550 NE-552 

NE-572 

NE-542 

NE-621 (Med.Img) 

2001-2002 NE-552 (Internet) 

2002-2003 NE-552 

2003-2004 NE-550 NE-552 

2004-2005 NE-552 

2005-2006 NE-542 NE-552 (local and distance) 

2006-2007 NE-542 NE-552 

NE-621 (Med. Img.) 


NE-621(Uncert.Anal) NE-550 

2008-2009 NE-550 NE-552 

NE-542 


2010-2011 NE-542 NE-552 

NE-621 (Special Topic) 

SERVICE ON COMMITTEES (Incomplete) 

Doctor of Philosophy Committees 

Willie Tan King, Ph.D., May, 1980 

Feasibility of 252 Cf Source Driven Neutron Noise Measurements 

Robert S. Howell, Ph.D., May, 1981 

Equivalent Source Estimation for use in Solving the Fixed Source Boltzmann Transport Equation by 

Monte Carlo Methods 

Amir Sassan Mobasheran, Ph.D., December, 1981 

Thermal Design and Heat Transfer Analysis of the OC-6 Graphite Irradiation-Induced Creep Test Capsule 

Edward James Allen (Mathematics), Ph.D., August 1983 

A Galerkin Method for Numerically Solving the Energy-Dependent Neutron Transport Equation 

Huan-Tong Chen, Ph.D. May 1986 

A Generalized Approach to the Biased Adjoint Monte Carlo Calculation 

Mohammed Hassan Abu-Shehardeh, Ph.D., August, 1986 

Development of a Dynamic Model for the Advanced Neutron Source Reactor 

41

Wilson Jose Vieira, Ph.D., December 1989 

A General Study of Under Sampling Problems in Monte Carlo Calculations 

Richard T. Wood, Ph.D., December1990 

A Neutron Noise Diagnostic Methodology for Pressurized Water Reactors 

Daniele Ugolini, Ph.D., December, 1991 

A Methodology for the Solution of Nonlinear Two-Point Boundary Value Inverse Problems in Science and 

Engineering 

Mohamad Ahmed Abdalla, Ph.D., August 1991 

A Lagrangian Based Nonlinear Control Algorithm: Application to the Advanced Liquid Metal Reactor 

Javier Reyes-Jemenez, Ph.D., August, 1992 

Knowledge-Based Radiological Planning and Optimization Using Fuzzy Logic 

Daniel F. Hollenbach, Ph.D., July 15, 1992 

Vectorization Methods Development for a New Version of the KENO-V.a Criticality safety Code 

Mohamed Ibrahim Abdelhai, Ph.D., May 1993 

A New Methodology Based on Fuzzy Set Theory and Fault Tree Analysis for Failure Diagnosis in Nuclear 

Power Plants 

Cynthia M. McIlvaine (Env. Eng.), Ph.D., August, 1993 

Magdi A. Essawy, Ph.D., May 24, 1994 

Artificial Neural Network for System Modeling Monitoring and Control 

Benan Basoglu, Ph.D., May, 1995 

Parallel Methods Development for a New Version of KENO-V.a Criticality Safety Code 

Joshph G. Kreke, (Physics), Ph.D., December, 1995 

Muon-Pion Discrimination Using a Sampling Calorimeter and Discriminant Analysis Techniques 

Mamun F. Amer, Ph.D., December, 1996 

A Bayesian Approach to the Biokinetic Models of Internally Deposited Radionuclides 

Mike Clagget, (Env. Eng.), Ph.D., February 23, 1996 

Developing a New Dispersion Model for Predicting Air Pollution Levels in the Cavity Region of a 

Building Wake and Complex Terrain 

Rose Ann Boll, (Chemistry), Ph.D., April 1996 

Development of an Improved Environmental Actinide Separation Method 

Michael G. Stabin, Ph.D., December, 1996 

Stochastic Track-Structure Simulation Methods and the Determination of Product Yields in the Radiolysis 

of Water Containing Various Solutes 

Mamun F. Amer, Ph.D., December, 1996 

A bayesian Approach to the Biokinetic Models of Internally Deposited Radionuclides 

42

Kadir Kavaklioglu, Ph.D., December, 1996 

Optimal Fuzzy Control Design Using Simulated Annealing and Application to Feed water Heater Control 

Charles L. Bentley, Ph.D., December, 1996 

Improvements in a Hybrid Stochastic/Deterministic Method for Transient, Three-Dimensional Neutron 

Transport 

Michael E. Dunn, Ph.D., December, 1996 

Development of a Continuous Energy Version of the Monte Carlo Code KENO V.a 

Steven Michael Claggett, (Env. Eng.), Ph.D., May, 1996 

Developing a New Dispersion Model for Predicting Air Pollution Levels in the Cavity Region of a 

Building Wake and Complex Train 

Georgi Metodiev Daskalov, Ph.D., August, 1996 

Propagation of Ultrasonic Pulses in Flawed Media: Applications to Nondestructive Testing and Evaluation 

Aucyone A. DaSilva, Ph.D., December, 1997 

An Integrated Approach for Plant Monitoring and Diagnosis Using Multiresolution Wavelet Analysis 

Bruce Clemens, (Educational Psychology), Ph.D., May, 1997 

for Radioactive Metal 

Jonathan Dyke, (Eng. Science), Ph.D., December, 1997 

Dosimetry and Stability Studies of the BNCT Agent F-BPA-Fructose using PET and MRI 

Linda A. Lewis, (Chemistry), Ph.D., December, 1997 

99 Tc Bioassay by Inductively Coupled Plasma Mass Spectrometry (ICP-MS) 

Shili Xiao, Ph.D., May, 1998 

Bayesian Analysis of Relative Toxicity of 239 Pu and 226 Ra with Dependent Competing Risks 

John K. Mattingly, Ph.D., May 1998 

High Order Statistical Signatures from Source-Driven Measurements of Subcritical Fissile Systems 

Lance David Weems, Ph.D. December 1998 

Tomographic Applications of Wavelets in Passive Nondestructive Assay of Radioactive Waste 

Jonathan Mich Duffey, (Chemistry), Ph.D., May 1999 

Advances in Alpha Liquid Scintillation Spectrometry 

Ali Seyfettin Ebay, Ph.D., May 1999 

Multi-Sensor Fusion for Induction Motor Aging Analysis and Fault Diagnosis 

Paulo Brasko Ferreira, Ph.D., May 1999 

Incipient Fault Detection and Isolation of Sensors and Field Devices 

J. Daniel March, Ph.D., August 2000 

Application of the Electrostatic Separation of Recoil Atoms to the Separation of the 225 Ac- 217 At- 213 Bi 

43

Decay Series 

Peter Michael Smith, Ph.D., August 2000 

The Development of a Lutetium Recovery Plant 

Chester R. Ramsey (2000) Implementation of a Video Based Respiratory Gating System for Radiation 

Therapy 

John S. Neal, Ph.D., May 2001 

Forecasting Dose-Time Profiles of Solar Particle Events Using a Dosimetry-Based Bayesian Forecasting 

Methodology 

Hanna Moussa (2001) Estimation of Absorbed Fraction to the Anterior Nose from Inhaled Beta Emitters 

Ryan Brame (2002) Bayesian Methods for Internal and External Radiation Dosimetry 

Daniel L. Stephens (2003) Measurements of Secondary Charged Paraticle Fragmentation Cross Sections 

produced by High Energy Heavy Ions Using Silicon Strip Detectors 

Jennifer L. Hoff (2003) Prediction of Dose-Time Profiles for Solar particle Events Using Neural Networks 

Mark A. Buckner (2003) Learning from Data With Localized Regression and Differential Evolution 

James Patrick McClanahan (2004) Advanced Eddy Current Test Signal Analysis for Steam Generator 

Tube Defect Classification and Characterization 

Thomas Miller (2004) Comprehensive Cross Section Database Development for Generalized Three 

Dimensional Radiation Transport Codes 

Dustin Garvey 

Alexander Usynin (Generic Prognostic Approach to Remaining Useful Life Prediction, Ph.D.) 

Trent Nichols (Dec 2008) 

The Microdosimetry of Boron Neutron Capture Therapy 

Carley Harris (December 2008) 

A Novel Tool for Predicting Which Head & Neck Patients Will Require Adaptive Radiation Therapy 

Sirikul (Indi) Sriprisan (Dec 2008) 

An Improved Knockout-Ablation-Coalescence Model for Prediction of Secondary Neutron and Light-Ion 

Production in Cosmic Ray Interactions 

Youssef Charara (May 2009) 

Sergio Ricardo Pereira Perillo (Oct 2010) 

Multi-Modular Integral Pressurized Water Reactor Control and Operational Reconfiguration for a Flow 

Control Loop. 

44

Master of Science Committees 

Hashem Mehrdad Hashemian, M.S., December, 1977 

In-Situ Response Time Testing of Platinum Resistance Thermoneters In Nuclear Power Plants 

David L. Kirby, M.S., December, 1977 

Gamma-Ray Energy Deposition Studies Using CaF2:Mn Chip Thermoluminescence Dosimeters 

Michael Kiser, M.S., May, 1977 

Investigation of Identifyability of Various Parameters in Pressurized Reactors with Applications to 

Milstone 2 and Oconee I Nuclear Power Plants 

Bryan Broadhead, M.S., May,1978 

Sensitivity and Uncertainty Analysis Applied to the Thermal Column of the National Bureau of Standards 

Reactor: Parts 1-4 

Jeng-Chang Cherng, M.S., May, 1978 

An Investigation of the Feedwater Controller and the Non-Linear Effects of a U-Tube Steam Generator 

Model 

Quang An Huynh, M.S., May, 1978 

A Cost/Benefit Analysis for Dynamic Testing in the Fast Flux Test Facility 

Sherrell Greene, M.S., May, 1979 

The Design, Implementation and Cost/Benefit Analysis of a Dynamic Testing Program in the Experimental 

Breeder Reactor-II 

Willis P. Poore, M.S., August 1979 

Resistance Thermometer Characteristics and Response Time Testing 

Thomas Magette, M.S., May, 1979 

Reports in lieu of thesis 

Ronald E. Pevey, M.S., May 1979 

(Problems in lieu of thesis) 

Vernon Guthrie, M.S., May 1979 

A Reliability Analysis on the CRBRP Annulus Filtration System 

James Dougles Smith, III, M.S., May 1980 

Processing ENDF/B-V Uncertainty Data into Multigroup Covariance Matrices 

John R. White, M.S. December, 1980 

The Development, Implementation and Verification of Multicycle Depletion Perturbation Theory 

Katrina Michelle P. Johnson, M.S., December 1981 

Methodology for Reliability Analysis of Systems Undergoing a Phased Mission 

Kimuel L. Hill, M.S. December, 1982 

Fuel Cycle Economic Analysis for the Oak Ridge National Laboratory BOLD Venture Core Analysis 

System Analytic Solution for BWR Gamma Thermometer Transient Heat Equation 

45

Bernard J. Weber, M.S. May, 1982 

A Reliability Analysis of the Clinch River Breeder Reactor Plant Power Transmission System 

Mounir Jamil Mneimneh, M.S., December 1984 

Modular Modeling 

Martin Allen Stutzke, M.S., December 1984 

Seismically Induced Core-Damage Accidents in the Clinch Riber Breeder Reactor Plant 

Robert Dale Timmerman, M.S., December 1986 

Problems in lieu of thesis 

Majed Nasr Natour, M.S., December 1986 

Modeling and Testing of Industrial Thermometers 

Meraj Rahimi, M.S., May 1986 

The Functional Interpolation Method for Reactor Core Physics 

Nelson Douglas Woody, M.S., December 1987 

Development of a Nuclear Engineering Computational System for the University of Tennessee 

Daniele Ugolini, M.S., August, 1987 

Monte Carlo Criticality Calculations Using a Parallel Processor Computer 

Ross Christopher Robinson, M.S., August, 1988 

(Projects in lieu of thesis) 

Kevin Howard Reynolds, M.S., May 1990 

Criticality Safety Studies of a Proposed Uranium-Zerconium Metal Alloy Fuel Production Facility 

Bradley W. Dolan, M.S. December 1990 

A Statistical Method for Imputation of Uranium-235 Activity in the Lung Using Urinalysis Data 

Michael Ray Corum, M.S., December, 1990 

Applications of the Very High Temperature Reactor in the Transportation of Fuels Industry: A means to 

Reduce U.S. Oil Imports and Carbon Dioxide 

Agus Cahyono, M.S., December 1991 

Application of Neural Networks to Measurements of Temperature Sensor Response Time 

Wu Yan, M.S., December 1991 

Development of a Dynamic Compensated Temperature Sensor 

Aidong Wei, M.S., May 1991 

Analysis and Condition Monitoring of Air-Operated Valves 

Saleh Afif Alafifi, M.S., May 1992 

(Problems in lieu of thesis) 

46

Timothy Eugene Valentine, M.S., August 1992 

Feasibility of Monitoring Subcriticality During Fueling of the Advanced Neutron Source Reactor 

Jupiter Sitorus Pane, M.S., December, 1992 

Estimation of a Average Hotleg Temperature in PWRs Using Spectral Features of Reactor Coolant 

Pressure Signal 

Christopher M. Smith,(Env. Eng.), M.S., August, 1993 

Kadir Kavaklioglu. M.S. April 8, 1993 

Performance Monitoring of Pressurized Water Reactors Using Artificial Neural Networks 

Christopher F. Haught, M.S. May 4, 1993 

Engineering Practice Reports 

Christopher L. Black, M.S. December 16, 1993 

Backpropagation Neural Network Sensitivity Analysis and Process Modeling with Application to Kingston 

Fossil Power Plant Net Unit Heat Rate Optimization 

Ernest P. Elliott, M.S. November 23, 1993 

Validation of KENO V.A for Highly-Enriched Uranium Systems with Hydrogen and/or Carbon 

Moderation 

Ernest P. Elliott, M.S., August, 1993 

Validation of KENO V.A for Highly-Enriched Uranium Systems with Hydrogen and/or Carbon 

Moderation 

Michael J. Plaster, M.S. November 15, 1993 

Analysis of a Hypothetical Criticality Accident in a Waste Super-Compactor 

Ricky Lynn Summitt, M.S., April 15, 1994 

Assessment of the Containment Response of an Advanced PWR to Selected Sever Accident Sequences 

Alan Wilkinson, M.S. April 22, 1994 

(Engineering Practice Reports) 

Installation of SCALE 4.1 on a University of Tennessee Mainframe Computer System 

Dose Estimate Improvements for Nuclear Criticality Accidents 

Daniel A. Smith, M.S., May 20, 1994 

(Engineering Practive Reports) 

Development of an Improved Model for Predicting Fission Product Release from High Temperature Gas 

Cooled Reactors 

John Joshph Arnish, M.S. May 23, 1994 

Bayesian Estimation of Dose-Rate Effectiveness Factors 

Jerry Lichtenwalter, M.S., May 25, 1994 

Performance Modeling of High-Temperature Gas-Cooled Reactor Fuel During Accidental Simulations 

Michael E. Dunn, M.S., June 1, 1994 

Nuclear Criticality Safety Evaluation of the 233U Inventory at the Oak Ridge National Laboratory Using 

47

ENDF/B-V Cross Sections 

Robert Cooper, M.S., June 13, 1994 

Bayesian Techniques for Imputation of Missing Occupational Dose/Exposure Data 

Charles L. Bentley, M.S., June 14, 1994 

Shutdown Mechanisms for a Hypothetical Criticality Accident Involving Highly Enriched Uranium 

Powder 

Sedat Goluoglu, M.S., July 20, 1994 

(Reports in lieu of thesis) 

1) Improved Neutronics Calculations of the High Flux Isotope Reactor 

2) Installation and Testing of MCNP on a Sun-SPARC-10 Workstation 

3) Installation and Testing of BOLD-VENTURE on IBM 386 and Pentium Machines 

Michael E. Murray, (Env. Eng.), M.S., December, 1994 

The Evaluation of Electret Inonzation Chambers as a Field Screening Method for Samples Containing 

Natural and Depleted Uranium 

Laura J. Tryboski (Swanke), M.S., December 1994 


1) Radiological Dose Evaluation for the D&D Facilities at the Nevada Test Site 

2) Correlation of FIDLER Measurements with Analytical Soil Concentrations 

Shiemei Xiao, M.S., ~December, 1994 

Estimation of Low-Level Net Counting or Exposure Rates 

Ali Seyfettin Erbay, M.S., December 1994 

A PC-Based Signal Validation System for Nuclear Power Plants 

Magdi A. Essay, M.S., August, 1995 

Artificial Neural Networks for System Modeling, Monitoring and Control 

John Mattingly, M.S., February 1995 

Time-Frequency Analyses of Nonstationary Signals 

Richard Alan Kleinfelter, (Env. Eng.), M.S., April 21, 1995 

(Non-Thesis) 

Andreas Theodoros Taprantzis, M.S., April, 1995 

The Advanced Zoned Tokamak with Edge Control: The AZTEC Concept 

Greg Swaggerty, M.S., ~December, 1995 

Surveillance and Analysis of Multivariate Processes Using Digital Signal Processing 

Michael Edward Howard, M.S., April 1995 

Calibration of Bacteria Survival to Radiation Using Bayesian Procedures 

Richard Alan Kleinfelter,(Env. Eng.), M.S., April 1995 

(Non-Thesis) 

48

Emmert L. Brant,(Env. Eng.), M.S., November, 1995 

Meteorological Conditions Influencing Ground-Level Ozone Concentrations 

Andreas Theodoros Taprantzis, M.S., ~December, 1995 

The Advanced Zoned Tokamak with Edge Control - The Aztec Concept 

Emmert L. Brant (Env. Eng.), M.S., December, 1995 

Meteorological Conditions Influencing Ground-Level Ozone Concentrations 

Miodrag Glumac, M.S., December, 1995 

Automated Diagnosis of Motor-Operated Valves Using Motor Power Signature 

Teresa Cook Perry, (Env. Eng.), M.S., November, 1995 

A Quantitative Uncertainty Analysis for the Assessment of Risk Associated with Radionuclide Releases 

from the I-1435 Incinerator at Oak Ridge, Tennessee - Human Inhalation Pathway Analysis 

Yunnhon Lo, M.S., May, 1996 

Measurement of Radon Daughters - A Bayesian Approach 

C. A. England, M.S., November 15, 1996 

Radiological Characterization of a Uranium Processing Facility 

Steven G. Bier, M.S., August, 1996 


Neal Zap, M.S., December, 1997 

Solar Particle Event Dose Distributions: Parameterization of Dose-Time Profiles, with Subsequent Dose- 

Rate Analysis 

Scott Snowden, M.S., December, 1997 

Signature Monitoring and Automated Diagnosis of Motor Operated Valves 

Mark S. Wyatt, M.S., December, 1997 

Characterization of an Enriched Uranyl Fluoride Deposit at the Former K-25 Enrichment Plant Using 

Active Neutron Interrogation Techniques 

Garth mark Forde, M.S., August 1997 

Application of Neural Networks to Predict Solar Particle Event Doses 

Mark S. Wyatt, M.S., December, 1997 

Characterization of an Enriched Uranyl Fluoride Deposit at the Former K-25 Enrichment Plant Using 

Activity Neutron and Gamma Interrogation Techniques 

Edward Neal Zapp, M.S., December 1997 

Solar Particle Events Dose Distributions: Parameterization of Dose-Time Profiles with Subsequent Dose 

Rate Analysis 

William L. Maxson II, M.S., December, 1997 

Equivalent Sphere Approximations for Skin, Eye and Blood Forming Organs Dose Estimates in Space 

Radiation Protection Studies 

49

Chester R. Ramsey, M.S., May, 1998 

Optical Model Methods of Predicting Nuclide Fragment Production for Space and Radiation Therapy 

Applications 

Cynthia M. Maples, M.S., May, 1998 

Influence of Dose Uncertainty on Dose-Response Parameter Estimation 

M.S. Thesis or Engineering Practice Project Titles (Completed in FY99) 

Brian Bailey “A 1991 Plutonium Wound Incident: A Case Study” 

Dax Jolly “Rotating Machinery Misalignment Detection and Prediction Using 

Motor Power Spectrum” 

James McClanahan “Monitoring Electric Motor Aging Using Vibration and Current 

Signatures” 

Anne Robinson-Silber “Long-Term Thermal Aging of Resistance Temperature Detectors” 

Daniel Stephens Project #1 – “Imputation of Rare Cancers in A-Bomb Survivors with a 

Hierarchial Model” 

Project #2 – “Experimental Measurements of Charged Particle Fluence 

Spectra for NASA Targets” 


Deborah Bentzinger (1) “Design of a Californium Source-Driven Measurement System for the 

Accountability of Material Recovers from the Molten Salt Reactor 

Experiment Facility Auxiliary Charcoal Bed.” 

(2) “ORNL’S Benchmark Calculations of the Japanese High Temperature 

Engineering Test Reactor Startup-Core Physics with Monte Carlo 

MCNP4a.” 

Ryan Brame “Technical and Procedural Initiation/Implementation of Predictive 

Maintenance at the High Flux Isotope Reactor” 

Daniel Evans “Pyxis: A Java Program to Provide a Windows Environment for Performing 

Linked Engineering Calculations” 

Roger Gard “SPALLDKZ: A Nuclear Decay Model” 

Rodney Harvill “Thermoacoustic Waves in Liquid Metal Targets for High Power Spallation 

Neutron Sources” 

Jennifer Hoff (Parsons) “Modeling the Wall Effects of a Tissue Equivalent Proportional Counter 

Using MCNP” 

William Pointer “Evaluation of Low Pressure Leak Flows in Metallic Vacuum Vessels for 

Detection Systems Using Helium Dissolved in an External Water Cooling 

Jacket” 

50

Kenneth Richardson (1) “Cumulative Doses from Large Solar Particle Events During Interplanetary 

Missions” (2) “Virgil C. Summer Nuclear Station Proposal for Approval to 

Dispose of Material Contaminated with Very Low Levels of Licensed 

Radioactive Material by Alternative Means of Disposal” 

Andrew Stephan “Characterization and Evaluation of a Microcantilever Radiation Detector” 

Mat Tamimi “Bayesian Analysis of a Radiation Detection Problem” 


William Bird “Development of an Optical Surface Method for Transport Calculations" 

Karen Brumley “Engineering Practice Project #1, "MARCUS Code Project" Engineering 

Practice Project #2, "Boron in a Criticality Safety Validation" 

Thomas Miller “Radiation Transport Analysis of the SNS Target Station Neutron Beam 

Line Shutters.” 


G. Scott Braley “Coalescence Effects on Neutron Production in High Energy Nucleus- 

Nucleus Collisions” 

Robert Elwood “Delayed Critical Unreflected and Unmoderated Uranium Metal Single 

Cylinder and Interacting Cylinders (Two) for Evaluation of Neutron 

Transport Methods and Associated Cross-Section Data” 

Baofu Lu “Development of an Incipient Fault Detection and Isolation Method for the 

Steam Generator System of a Nuclear Power Plant” 

Anne-Marie Shatara (1) “Analyses of Liquid Radwaste System Total Suspended Solids Data for 

Diablo Canyon Power Plant” (2) “Construction of an Informational Nuclear 

Fuel Cycle Webpage” 

Susan Turner “Installation, Testing, and Demonstration of Discrete Ordinates Particle 

Transport Software (PARTISN 2.64/DANTSYS 3.1) For Use on the Y-12 

National Security Complex SGI Supercomputer” 

Wesley Williams “Conceptual Design and Layout of the Balance of Plant for a Generation IV 

Nuclear Power Plant Using the Westinghouse International Reactor, 

Innovative & Secure (IRIS)” 


Shane Parkey (1) “Development of a Nuclear Criticality Safety Training Manual,” (2) 

“Validation of Nuclear Criticality Safety Benchmarks for Y-12,” and (3) 

51

“Development and Analysis of Graphite Nuclear Criticality Benchmark 

Problems” 

Jennifer L. Wilson (1) “On Line Mechanical Maintenance of Condenser Cleanliness” 

(2) “Difference in Effect of Zinc Injection on Shutdown Release 

Rates in a PWR Relative to Core Duty” 

Ke Zhao “Development of a Data Driven Multiple Observer and Causal 

Graph Approach for Fault Diagnosis of Nuclear Power Plant 

Sensors and Field Devices” 


Joseph Bowling “Fault Detection and Isolation Expert System and Kernel 

Smoothing Techniques to Monitor the Continuous Automated 

Vault Inventory System (CAVIS)” 

Jarrod D. Edwards “Analysis of Neutron Reflection in Correlation Measurements” 

Katherin L. Goluoglu “Revitalization and Status of TDKENO, a Hybrid 

Stochastic/Deterministic Computer Code for Transient, Three- 

Dimensional Neutron Transport” 

Jeffrey L. Goodman “Design of a Collimator for a Hand-Held Enrichment Meter” 

Thomas J. Harrison “The Sequential Probability Ratio Test (SPRT) In Feature Extraction 

And Expert Systems In Nuclear Material Management” 

Robert Schlicht “Development of MCABRE: A Monte Carlo Radiation Transport 

Method to Estimate Radiation Dose in a Building” 

Martin Williamson “Transportable Modular Balance of Plant Study for Small Nuclear Power 

Plants” 

Allan B. Wollaber “Burnable Poison Design for the International Reactor, Innovative and 

Secure (IRIS)” 


Charles W. Alvord Calculations in Support of Design of a Novel Solid-State Detector 

Architecture for Microfluidic Radiochromatography 

Michael D. Elo Spent Fuel Benchmarks for SCALE5 TRITON Validation 

Chrystomes Kahambwe Investigation of Zircaloy-4 Doped with Metallic Burnable Poisons 

Bartley D. Stewart Radiation Diagnostics at the Decade Radiation Test Facility 

John Edwards (Dec 2005) 

52

Determining Heavy Ion Fragmentation Cross Sections by the Use of Weak Factorization 

Theodore Nichols (May 2005) 

Using Artificial Intelligence Methods to Predict Doses From Large Solar Particle Events in Space 

M.S. Thesis or Engineering Practice Project Titles (Completed in CY06) 

Ralph DeMeglio (May 2006) 

Amy Street (May 2006) 

Solar Particle Event Flux Distributions in Various Shielding Materials 

Bo Lu (May 2006) 

Theoretical Study of Noble Gas Bubble Behavior in Mercury 

Matthew Francis (May 2006) 

Long-Term Station Blackout Sequence and Mitigation MELCOR Model 

Brian Timm (May 2006) 

Galactic Cosmic Ray Transport Through Aluminum, Carbon Foam, Polyethylene, and Kevlar Shielding 

Rebecca Seibert (May 2006) 

Development of NUREG/CR-6895 “Technical Review of On-line Monitoring Techniques for Performance 

Assessment Volume I: State-of-the-Art.” 

Dang Ho (Dec 2006) 

Farley Dropped Rod Recovery Relaxation Analysis 

Faley Unit 2 CASMO-SIMULATE Modeling 

Nishka Devaser (Dec 2006) 

System Parameter Review and Optimization: BDMS Confidence Level Estimator Quality 

Analytical Evaluation of the Effect of Uranium Deposits on a Non-Intrusive Fissile Mass Flow Monitor 

Clarence R. Willis (Dec 2006) 

Various Treatments of Epithermal Scattering From Hydrogen in Water 


Bryan Taylor (April 2007) 

Part I: An Engineering Practice Project Presented for Partial Fulfillment of the Requirements for the 

Master of Science Degree in Nuclear Engineering 

Part II: Reconstruction of PAD: A One-Dimensional, Coupled Neutronic-Thermodynamic-Hydrodynamic 

Computer Code 

Xiaojia Xu (April 2007) 

Development of a Dynamic Model of the SP-100 Reactor System for Control Design and Fault Monitoring 

Dustin Garvey (April 2007) 

An Integrated Fuzzy Inference Based Monitoring, Diagnostic, and Prognostic System 

53

Robert Joseph (April 2007) 

Dose Equivalent Estimates for Possible Human Missions to Mars 

Fan Li (December 2007) 

Abnormal Situation Prevention of Process Units of Fossil Power Plants Using Data Mining Techniques 

David Hooper (December 2007) 

Cavitation of Mercury in a Centrifugal Pump 


Richard Taylor (May 2008) 

An Engineering Practice Project Presented for Partial Fulfillment of the Requirements for Master of 

Science Degree 

Brandon Grogan (May 2008) 

Estimating the Mass of UO3 Powder in a Container Using MCNP-PoliMi Simulations of NMIS 

Measurements 

Phil O’Bryan (May 2008) 

Reactivity Effects of Down Blending Enriched Uranium with Depleted Uranium 

Charles Denyer (Aug 2008) 

Nuclear Energy: An Economic and Environmental Cost Comparison Analysis with Fossil Fuels 

The International Atomic Energy Agency and the Safeguarding Process 

Thomas Copinger (Aug 2008) 

Improved Algorithm for Traceability Measurements in aUF6 Flow Pipe 

Susan King May (2008) 

Validation and Analyses of the SCALE 5.1 Platform for Criticality Safety of New and Spent Fuel Storage 

Analyses for Westinghouse Electric Company 

Analysis of Experimental Basis For Licensing 5-10% Enriched Commercial Nuclear Reactor 

M.S. Thesis or Engineering Practice Project Titles (Completed in 2009) 

Robert Woolley (May 2009, Defense in November 2008) 

Optimal Design of Mobile Nuclear Reactor Engines to Power Manned Vehicles On Mars 

Jamie Anderson (October 2009) 

M.S. Thesis or Engineering Practice Project Titles (Completed in 2010) 

James Hinderer (May 2010) 

Radioisotopic Impurities in Promethium-147 Produced at the ORNL High Flux Isotope Reactor (HFIR) 

54

Josh Marshall (Aug 2010) 

FLUKA Benchmarking Studies of Secondary Neutron Production 

Mark G. Jadick (Dec 2010) 

Performance Testing and Validation Plan of the Holdup Measurement System 4 for the K-25 East Side 

Process Gas Piping. 

Thesis and Engineering Practice Project Titles (Completed in 2011) 

Kirsten Peña 

Prompt Neutron Time Decay in Single HEU and DU Metal Annular Storage Castings 

Patrick D. Brukiewa 

235U Mass Flow Rate Measurements in GCEPs through Passive Monitoring of Process Equipment and 

Gamma Spectroscopy 

Josh Cates 

Studying Timing Resolution of an Associated Particle Detector for Fast Neutron Imaging 

Matthew T. Cook 

Modernization and Development of a Fallout Prediction System for water Surface Nuclear Explosions 

Jon Garrison 

Monte Carlo Analysis of Thermochromatography as a Fast Separation Method of Activation and Fission 

Products for Nuclear Forensics 

M.S. & Ph.D. Committees (Completed in 2012) 

Brandon Holden (May 2012)(MS) 

Hybrid Fuel Assembly Design and Hybrid Reactor Core Analysis Parts I and II 

Jamie Alicia Anderson (May 2012)(Ph.D.) 

Analysis of Measurements from the CRATER Instrument on the LRO Spacecraft using Space Radiation 

Transport Codes 

Joe Bowling (May 2012)(Ph.D.) 

Leksell Gamma Knife Treatment Planning via Kernel Regression Data Mining Initialization and Genetic 

Algorithm Optimization 

Matthew Beach (May 2012)(MS) 

Measuring the Dose Reduction Capabilities of Various Targets When Using a 1000 MeV/nucleon 

Iron-56 Beam 

Liang Zuo (May 2012)(Ph.D. Electrical Engineering) 

Low-Voltage Bulk-Driven Amplifier Design and Its Application in Implantable Biomedical Sensors 

Cole Gentry (May 2012)(MS) 

An Investigation of the use of Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in 

Pressurized Water Reactors 

55

Braden Brown (May 2012)(MS) 

Project 1: Warhead Counting for Treaty Verification Using Fast-Neutron Coded-Aperture Imaging 

Project 2: A Methodology of Investigating Resources for Tracking of Illicit Radiological and Nuclear 

Materials at International Crossings. 

56

Vita - College of Engineering - The University of Tennessee, Knoxville

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