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solving the quantum three-body problem, using the Bonn-B NN potential and the three-nucleon Canton- Schadow force. A multi-channel algebraic scattering (MCAS) methodology is applied to obtain a better understanding of low-energy neutron scattering from 16 O (and 18 O). LD 2 4:00 PM Nuclear Data Library Effects on High-Energy to Thermal Flux Shapes around PWR Control Rod Tips A. Vasiliev, H. Ferroukhi, T. Zhu Paul Scherrer Institut The development of a high-fidelity computational scheme to estimate the accumulated fluence at the tips of PWR control rods (CR) has been initiated at the Paul Scherrer Institut (PSI). Both the fluence from high-energy (E>1 MeV) neutrons as well as for the thermal range (E
kinetic model based on Avery-Cohn model is simple, calculable. The model introduces simple probability relationships essential to calculating the coupling parameters between core and reflector [1] and derives the reflected-core inhour equation which contains multiple decay modes. However, Spriggs model cannot describe well the multiple time constants of the thermal reflected reactor. In this kind of reactor, thermal neutrons with long lifetime contribute much to the time constant. Because of importance of thermal neutrons in such fast-thermal reactor, we present a simplified two-group; two-region kinetic model (2G2R) based on Spriggs model, and rewrites the reflected-core inhour equation. With the help of the numerical method, we perform the analytical calculation on the coupling parameters, neutron lifetimes and first and secondary time constant of a hypothetical reactor, and compared with the numerical methods, the Monte-Carlo method and the stochastic neutron kinetics. The results of 2G2R model agree well with the Monte-Carlo time fitting method which can be thought as an experiment in computer. [1]. G. D. Spriggs et al., “Two-Region Kinetic Model for Reflected Reactor”, Ann. Nucl. Energy, 24, 205, (1997). LD 4 4:40 PM ATR HEU and LEU Core Kinetics Parameters Calculation by MCNP5 Version 1.60 Adjoint-Weighted Method G. S. Chang Idaho National Laboratory C. R. Glass Idaho National Laboratory The Advanced Test Reactor (ATR), currently operating in the United States, is a high power research reactor used for nuclear material testing at very high neutron fluxes. Powered with highly enriched uranium (HEU), the ATR has a maximum thermal power rating of 250 MWth. Because of the large core fuel loading with 235 U ∼ 43 kg, the ATR is assessing the feasibility of converting HEU driven reactor cores to lowenriched uranium (LEU) cores. The present work investigates the impact on the safety related kinetic parameters of the LEU alternate Monolithic foil-type (U-10Mo) fuel with external 10 Be absorber (0.58 g) in fuel element side-plates, as compared to the HEU reference case. The calculated safety related kinetic parameters, such as the effective neutron generation time, Λeff , and the effective delayed neutron fraction, βeff , are of considerable importance in the fast transient safety analysis of the ATR. These parameters are typically calculated using deterministic codes. For complex nuclear systems, such as the ATR with its HEU/LEU fuel elements, water coolant, and beryllium (Be) reflector, the Monte Carlo method, specifically MCNP5 version 1.60, is the preferred calculation tool because of its ability to handle continuous energy cross-sections and detailed geometries. MCNP5 version 1.60 has a newly added option (KOPTS KINETICS=YES) to calculate the effective (i.e. adjoint-weighted) neutron generation time (Λeff ), and delayed neutron fraction (βeff ), which can be executed to accurately calculate the ATR HEU and LEU core’s kinetics parameters. In this work, the neutron generation time and delayed neutron fraction for ATR HEU/LEU core will be directly calculated using a single code, without having to generate energydependent cross-sections or approximate geometries. 1. Monte Carlo Codes (XCP-3), X Computational Physics Division, Los Alamos National Laboratory “MCNP5 - 1.60 - A General Monte Carlo N-Particle Transport Code”, Version 5/1.60, Forrest Brown, Brian Kiedrowski, Jeffrey Bull , “MCNP5-1.60 Release Notes,” LA-10-06235. 2. B. C. Kiedrowski, F. B. Brown, P.H. Wilson, “Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo,” LA-UR-10-01824, 2010. 3. “Upgraded Final Safety Analysis Report for the Advanced Test Reactor,” Idaho National Laboratory, SAR-153, 2011. 179
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ND2013 2013 International Nuclear D
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Session BF Evaluated Nuclear Data L
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Session DD Nuclear Structure and De
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Hale, G. n+ 12 C Cross Sections fro
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Domula, A. New Nuclear Structure an
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Session KC Evaluated Nuclear Data L
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MacCormick, M. Survey and Evaluatio
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ments. Ivanova, T. Uncertainty Asse
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Arnold, C. Precision Velocity Measu
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19 Abridged Agenda Sunday March 4,
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21 Tuesday March 5, 2013 Time Met E
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23 Thursday March 7, 2013 Time Met
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Book of Abstracts Session AA ND2013
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multi-foil Parallel Plate Avalanche
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A Regional Coupled-channel Dispersi
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show the versatility of the code in
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[h] Table 1: Comparison of all the
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step was to determine which detecto
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In an effort to maintain the qualit
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Advances in Reactor Physics Linking
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sponsored the work presented in thi
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A revolutionary nuclear data system
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done in Ref. [1]. We demonstrate th
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CD 4 2:40 PM Development of a Syste
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with a central cavity where small s
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C. Arnold, E. Bond, T. Bredeweg, M.
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DA 3 4:20 PM Characterization and P
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detectors at the newly constructed
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Lead and lead-based alloys are - am
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of the setup. One option explored i
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DC 2 4:00 PM Improved Capture Gamma
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DC 5 5:00 PM Thermal Neutron Cross
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M.R. Gilbert, L.W. Packer, S. Lille
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Correlations Between Nuclear Charge
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Community’s 7th Framework Program
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we achieve very good separation of
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analysis of neutron leakage spectru
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a lower nuclear temperature than th
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Tungsten occurs naturally in five i
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for the combined use of integral ex
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in XUNDL and bibliographic informat
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former case, more realistic covaria
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WInfried Zwermann, Kiril Velkov, An
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LA-UR-12-23712 The ENDF/B-VII.1 [1,
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comparison of results C/E of fissio
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Session GA Evaluated Nuclear Data L
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Session GC accelerator applications
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Session GD Antineutrinos Tuesday Ma
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M. Fallot, S. Cormon, M.Estienne, V
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for extraction of very rare isotope
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and neutron multiplicity, informati
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as Monte Carlo simulations, and inc
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on its surface. The amplification t
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direction was recently used at n TO
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were chemically separated and the 2
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Strontium-82 Production at ARRONAX
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A. Guertin, C. Duchemin, F. Haddad,
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expected via an (n,γ) reaction. Pr
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Shinsuke Nakayama, Shouhei Araki, Y
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specific feature of the procedure e
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good timing characteristics.Example
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Materials and Measurements, Retiese
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derive reliable covariances from ta
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Page 140 and 141: A significant breakthrough in our t
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Page 152 and 153: During more than four decades since
Page 154 and 155: KC 2 2:00 PM R-matrix Analysis for
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Page 160 and 161: source SINQ (Swiss Spallation Neutr
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Page 166 and 167: LA 5 5:00 PM Measurements relevant
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Page 182 and 183: LE 5 5:00 PM Method of Best Represe
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Page 186 and 187: Impact of the Energy Dependent DDXS
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the trends in the experimental data
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However, experiments often measure
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Statistical description of the gamm
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fragments formed are highly neutron
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F. Farget, J. Pancin GANIL, Caen, F
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ZPR-6/10 cores were applied as comp
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each nucleus in agreement with unce
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atios) is performed. In relation to
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school in science or engineering. I
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programs demanding only one compuls
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gamma-ray spectra will be theoretic
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RA 3 11:20 AM A Microscopic Theory
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Laboratory, Oak Ridge, Tenn., Novem
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Session RD Safeguards and Security
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Seeking Reproducibility in Fast Cri
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RE 4 11:40 AM Verification of Curre
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that a lot of them generally descri
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R. Hirschi, A. Hungerford, G. Magko
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- a density of levels too low for w
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the MONTEBURNS(1.0)-MCNP5-ORIGEN(2.
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The Nuclear Science References (NSR
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and applications using statistical
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Shielding objects are assembled fro
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The knowledge of neutron-induced re
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thus for the second time after the
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the global children health and cons
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Lawrence Livermore National Laborat
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The Russian Nuclear Data Library fo
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OECD Nuclear Energy Agency consider
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For experimental determination of t
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The European Activation SYstem has
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Neutron capture measurements of dys
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[1] H. Penttilä, P. Karvonen, T. E
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Measurement of Activation Cross Sec
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PR 66 Processing and Validation of
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law of the temperature ratio (RT =
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PR 74 Resonance Analysis of the 233
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Study of Various Potentials in Heav
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experimental data and for the produ
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fuel cycle impose tight requirement
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they do not satisfy (for example, b
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Differential Cross Sections for the
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extends the previous evaluation and
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various benchmark tests. The mainly
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PR 104 Evaluations for n+ 54,56,57,
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PR 109 Recent LAQGSM Developments a
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PR 113 Modelling of Spallation Sour
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Jagiellonian University, Reymonta 4
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PR 120 Coupled-Channel Models of Di
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PR 124 Nuclear Data Evaluation and
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physicist. - There is no perfect se
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Manturov, M.N. Nikolaev, A.M. Tsibo
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Vasiliev, W. Wieselquist and H. Fer
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Author Index 1, Vojtěch Rypar, PR
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HF 5, KD 4, LA 3, LA 6, LA 7, LA 8,
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Dunn, M. E., BF 4, RC 3 Dupont, Emm
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Gulliford, Jim, CE 1 Gunsing, Frank
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Kahl, David, HD 7 Kahler, A. C., CA
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Lehaut, G., PD 6 Leinweber, Greg, L
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Munkhsaikhan, J., HC 7 Mura, Luis F
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Prael, Richard E., PE 5 Praena, Jav
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Sheets, S., CF 2 Shen, Qingbiao, PC
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Typel, S., JA 3 Tyutyunnikov, S., L
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