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Volume 157

Number 3

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