ANS / Publications / Journals / Nuclear Science and Engineering

The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations

José M. Aragonés, Carol Ahnert, and Nuria García-Herranz

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE07-A2709

Comparison and Extension of Dancoff Factors for Pebble-Bed Reactors

J. L. Kloosterman, A. M. Ougouag

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 16-29

Technical Paper / dx.doi.org/10.13182/NSE07-A2710

Perturbation Theory Based on the Method of Cyclic Characteristics

M. Assawaroongruengchot, G. Marleau

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 30-50

Technical Paper / dx.doi.org/10.13182/NSE07-A2711

Time Series Analysis of Monte Carlo Fission Sources - III: Coarse-Mesh Projection

Brian R. Nease, Taro Ueki

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 51-64

Technical Paper / dx.doi.org/10.13182/NSE07-A2712

Gamma-Ray Production Cross Sections in Multiple Channels for Neutron-Induced Reaction on ⁴⁸Ti for E_n = 1 to 200 MeV

D. Dashdorj, G. E. Mitchell, J. A. Becker, U. Agvaanluvsan, L. A. Bernstein, W. Younes, P. E. Garrett, M. B. Chadwick, M. Devlin, N. Fotiades, T. Kawano, R. O. Nelson

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 65-77

Technical Paper / dx.doi.org/10.13182/NSE07-A2713

Calculation and Analysis of n + ^{180,182,183,184,186,nat}W Reactions in the E_n 250 MeV Energy Range

Yinlu Han, Yuyang Shi, Zhengjun Zhang

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 78-94

Technical Paper / dx.doi.org/10.13182/NSE07-A2714

Vacuum Interface Analysis of a Windowless Spallation Target for Accelerator-Driven Systems

P. Michelato, E. Cavaliere, C. Pagani, E. Bari, A. Bonucci

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 95-109

Technical Paper / dx.doi.org/10.13182/NSE07-A2715

Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P

Roberto Orsi

Nuclear Science and Engineering / Volume 157 / Number 1 / September 2007 / Pages 110-116

Computer Code Abstract / dx.doi.org/10.13182/NSE07-A2716

Monte Carlo Variance Reduction for Energy Profile Calculation at the Electron Emission Due to Photon Radiation

Taro Ueki

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 119-131

Technical Paper / dx.doi.org/10.13182/NSE07-A2717

Stopping Criteria of Inactive Cycle Monte Carlo Calculations

Hyung Jin Shim, Chang Hyo Kim

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 132-141

Technical Paper / dx.doi.org/10.13182/NSE06-33

Secondary Neutron-Production Cross Sections from Heavy-Ion Interactions Between 230 and 600 MeV/Nucleon

L. Heilbronn, C. J. Zeitlin, Y. Iwata, T. Murakami, H. Iwase, T. Nakamura, T. Nunomiya, H. Sato, H. Yashima, R. M. Ronningen, K. Ieki

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 142-158

Technical Paper / dx.doi.org/10.13182/NSE07-A2719

Calculation and Analysis for p + ^{58,60,61,62,64}Ni Reactions Below 200 MeV

Chun-Tian Liang, Chong-Hai Cai

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 159-184

Technical Paper / dx.doi.org/10.13182/NSE07-A2720

Definition of Breeding Gain for the Closed Fuel Cycle and Application to a Gas-Cooled Fast Reactor

W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, H. van Dam

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 185-199

Technical Paper / dx.doi.org/10.13182/NSE07-A2721

Analyzing Nuclear Fuel Cycles from Isotopic Ratios of Waste Products Applicable to Measurement by Accelerator Mass Spectrometry

Scott M. Whitney, Steven Biegalski, Bruce Buchholz

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 200-209

Technical Paper / dx.doi.org/10.13182/NSE07-A2722

Multigroup Coupled Neutron-Gamma Cross-Section Library for Deterministic and Monte Carlo Borehole-Logging Analysis

Ivo Kodeli, Daniel L. Aldama, Piet F. A. de Leege, David Legrady, J. Eduard Hoogenboom, Pat Cowan

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 210-224

Technical Note / dx.doi.org/10.13182/NSE07-A2723

Escape and Transmission Probabilities in X-Y-Z Geometry

R. D. M. Garcia

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 225-235

Technical Note / dx.doi.org/10.13182/NSE07-A2724

A New System to Fuel Loading and Control Rod Pattern Optimization in Boiling Water Reactors

Juan José Ortiz, Alejandro Castillo, José Luis Montes, Raúl Perusquía

Nuclear Science and Engineering / Volume 157 / Number 2 / October 2007 / Pages 236-244

Technical Note / dx.doi.org/10.13182/NSE07-A2725

Reevaluation of Experimental Data and Analysis on Experimental Fast Reactor JOYO MK-I Performance Tests

Kenji Yokoyama, Akira Shono, Makoto Ishikawa

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 249-263

Technical Paper / dx.doi.org/10.13182/NSE06-109

Development of a Low-Enriched-Uranium Core for the MIT Reactor

T. H. Newton, Jr., M. S. Kazimi, E. E. Pilat

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 264-279

Technical Paper / dx.doi.org/10.13182/NSE07-A2727

Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmarks in an NPP with VVER-440 Reactor

S. Kliem, S. Danilin, A. Hämäläinen, J. Hádek, A. Keresztúri, P. Siltanen

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 280-298

Technical Paper / dx.doi.org/10.13182/NSE07-A2728

Application of Duality Principles to Reflector Homogenization

Jean Ragusa, Richard Sanchez, Simone Santandrea

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 299-315

Technical Paper / dx.doi.org/10.13182/NSE07-A2729

Development of a Novel Dynamic Simulink Model of the GT-MHR Core

Mehdi Reisi Fard, Thomas E. Blue, Don W. Miller

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 316-330

Technical Paper / dx.doi.org/10.13182/NSE07-A2730

A Thermal-Hydraulic Model for Catalytic Recombiners

Douglas W. Stamps

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 331-343

Technical Paper / dx.doi.org/10.13182/NSE07-A2731

Computational Modeling of Coupled Thermomechanical and Neutron Transport Behavior in a Godiva-Like Nuclear Assembly

S. C. Wilson, S. R. Biegalski, R. L. Coats

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 344-353

Technical Paper / dx.doi.org/10.13182/NSE06-28

Discrete Gamma Radiation in Interaction of 14.9-MeV Neutrons with Natural Copper

Hongyu Zhou, Fuguo Deng, Xiaoji Ding, Ming Hua, Qiaoge Zhu, Chao Wang, Qiang Zhao, Guoying Fan

Nuclear Science and Engineering / Volume 157 / Number 3 / November 2007 / Pages 354-367

Technical Note / dx.doi.org/10.13182/NSE07-A2733