Final Programme - Events
Final Programme - Events
Final Programme - Events
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Page 54 — Technical Sessions<br />
1. Uranium Mining Legacy: Long-Term Stewardship Challenges.<br />
E. Falck (IAEA)<br />
2. The Hungarian Approach to Long Term Monitoring and Maintenance<br />
J. Banik, I. Benkovics, G. Eroes (HUNGARIA)<br />
3. Preparation for Long Term Stewardship during the Active Mining Phase and Long Term<br />
Stewardship of the Orphan Sites<br />
P.Courtney, (CANADA)<br />
4. Saxony Regulator's Perspective of LTSM<br />
M.Kinze, S.Hurst (GERMANY)<br />
5. Long Term Monitoring/Stewardship Plans for the Sillamae Tailings Pond, Estonia<br />
T. Kaasik (ESTONIA)<br />
6. Uranium Mining Industry Perspective<br />
P.Landine (CANADA)<br />
7. A DOE Contractor's Perspective<br />
J.Moran (USA)<br />
8. Preparing Long Term Stewardship for the Brazilian Uranium-Mines<br />
H. Monken-Fernandes (BRAZIL)<br />
9. The WISMUT Strategy of Long Term Monitoring<br />
M. Paul (GERMANY)<br />
10. The Navajo Uranium Mill Tailings Remedial Action and Abandoned Mines Reclamation<br />
M. Roanhorse (USA)<br />
11. Preparing Long Term Stewardship in the Czech Republic<br />
J. Slezak (CZECH REPUBLIC)<br />
12. What is Stewardship? Preparing an LTSSM Plan for Former Uranium Mines in Northern<br />
Australia<br />
P. Waggitt (AUSTRALIA)<br />
WEDNESDAY 15:40 SESSION 46 ROOM 8<br />
ER SITE CHARACTERISATION AND MONITORING<br />
Co-Chairs: Wayne Einfeld, SNL (USA)<br />
Peter Booth, BNFL (UK)<br />
1. The Difficulties of Undertaking Site Characterisation on Operational Nuclear Licensed<br />
Sites - 4929<br />
P. Booth, R. Gordon, BNFL (UK)<br />
2. Characterization of NORM Contaminated Sites at the Syrian Oilfield: Depth Profiles and<br />
Leaching Processes - 4772<br />
M.S. Al-Masri, A. Aba, A. Al-Hamwi, H. Mukhallati, AECS (SYRIA)<br />
3. The Nature of Contamination of the Area in the Nearest Vicinity of Chernobyl NPP<br />
Destroyed Unit - 4737<br />
A. Skorbun, M. Panasyuk, O. Zhydkov, V. Gonchar, ITSC “Shelter”, Interdisciplinary<br />
Scientific and Technical Center (UKRAINE)<br />
4. Characterization of Current State of SRAW Storage Facilities of the Siberian Group of<br />
Chemical Enterprises and Radiological Situation on Adjacent Territory - 4840<br />
A. Bushuev, E. Petrova, T. Aleeva, V. Zubarev, I. Proshin, A. Kachanovsky, Moscow<br />
Engineering Physics Institute; E. ZaHarova, S. Ushakov, Institute of Physical Chemistry of<br />
Russian Academy of Sciences; V. Mescheryakov, A. Nikolaev, V. Hvostov, P. Savinyh,<br />
E. Kolobova, Siberian Group of Chemical Enterprises (RUSSIAN FEDERATION)<br />
Technical Sessions — Page 55<br />
WEDNESDAY 13:30 SESSION 47 ROOM 14<br />
ADVANCES IN VITRIFICATION OF HIGH-LEVEL WASTE<br />
Co-Chairs: Bill Holtzscheiter, WSRC/SRS (USA)<br />
Herve Masson, COGEMA (FRANCE)<br />
1. Vitrification of DOE Simulated Radioactive Waste by Induction-Heated Cold-Crucible<br />
Melter Technology - 4907<br />
R.A. Soshnikov, A.S. Aloy, A.V. Trofimenko, V.G. Khlopin Radium Institute; D.B. Lopukh,<br />
A.Y. Pechenkov, I.A. Loginov, St. Petersburg Electrotechnical Univ.; D.F. Bickford,<br />
C.C. Herman, W. Holtzsheiter, WSRC (RUSSIA/USA)<br />
2. Iron Phosphate Glass as Optional <strong>Final</strong> Waste Matrix for HLW - 4529<br />
T. Fukui, T. Ishinomori, N. Kubota, Y. Endo, Ishikawajima-Harima, Heavy Industries Co.;<br />
M. Sazarashi, K. Maruyama, S. Ono, K. Suzuki, IRI (JAPAN)<br />
3. Vitrification of HLW Produced by Uranium/Molybdenum Fuel Reprocessing in<br />
COGEMA’s Cold Crucible Melter - 4594<br />
R. Do-Quang, COGEMA; T. Flament, A. Prod’homme, SGN; V. Petitjean, F. Hollebecque,<br />
O. Pinet, CEA Marcoule (FRANCE)<br />
4. Lessons Learned Siting and Successfully Processing U.S. DOE Radioactive Waste Using a<br />
High Throughput Vitrification Process - 4836<br />
R. Prince, B.W. Bowan, II, Duratek, Inc. (USA)<br />
WEDNESDAY 13:30 SESSION 48 ROOM 15<br />
MODELING OF LONG-TERM PROCESSES IN THE DISPOSAL OF HIGH-LEVEL<br />
WASTE<br />
Co-Chairs: Murthy Devarakonda, Westinghouse TRU Solutions (USA)<br />
Pierre Van Iseghem, SCK-CEN (BELGIUM)<br />
1. Post-Leaching Studies of Defect Rodlets - 4641<br />
D. Wegen, D. Papaioannou, J-P Glatz, M. Amme, European Commission (GERMANY)<br />
2. A Radiolytic Modelling Intercomparison Exercise: Influence of Alpha Radiation on Spent<br />
Fuel Alteration Process - 4574<br />
J. Quiñones, CIEMAT; J. Merino, E. Cera, J. Bruno, ENVIROS; J. Cobos, CIEMAT-ITU;<br />
A. Martinez-Esparza, ENRESA (SPAIN/GERMANY)<br />
3. Evaluation of Uncertainty Associated with Spatially Variable Properties - 4561<br />
K. Kato, Tokyo Electric Power Company; T. Maeda, TEPCO Systems Corporation;<br />
H. Takase, Quintessa (JAPAN)<br />
4. Testing Safety and Performance Indicators in an Assessment of the Long-Term<br />
Performance of the Geological Disposal of Spent Fuel in Boom Clay - 4620<br />
X. Sillen, Belgian Nuclear Research Centre; J. Marivoet, SCK-CEN; W. Cool,<br />
P. de Preter, ONDRAF/NIRAS (BELGIUM)<br />
- Break -<br />
5. Long-Term In-Package Spent Fuel Criticality Calculations - 4575<br />
O. Wantz, Universite Libre de Bruxelles; O.F. Smidts, Association Vincotte Nuclear;<br />
A. Dubus, R. Beauwens, Service de Metrologie Nucleaire (BELGIUM)<br />
6. Comparative Quantitative Estimation of Engineered and Natural Barriers Influence on<br />
Ecological Safety of Long-lived Radwaste Underground Disposition - 4533<br />
T. Gupalo, V.P. Beygul, V.Yu. Konovalov, VNIPIPT (RF Minatom) (RUSSIA)<br />
7. Proceeding Toward a License Application for U.S. Nuclear Waste Repository: Total<br />
System Performance Assessment Approach - 4956<br />
J. McNeish, Bechtel-SAIC, LLC; P. Swift, SNL; R. Howard, Bechtel SAIC, LLC;<br />
D. Sevougian, D. Kalinich, R. MacKinnon, SNL (USA)