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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
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Criticality of a 237Np Sphere
Rene Sanchez, David Loaiza, Robert Kimpland, David Hayes, Charlene Cappiello, Mark Chadwick
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE08-A2734
On-the-Fly Diagnostics of Particle Population in Iterated-Source Monte Carlo Methods
Taro Ueki
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 15-27
Technical Paper | doi.org/10.13182/NSE08-A2735
Anisotropy and Particle Conservation for Trajectory-Based Deterministic Methods
R. Le Tellier, A. Hébert
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 28-39
Technical Paper | doi.org/10.13182/NSE08-A2736
A Coupled Diffusion Synthetic Acceleration for Binary Stochastic Mixture Transport Iterations
Todd S. Palmer
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 40-48
Technical Paper | doi.org/10.13182/NSE08-A2737
Global Results from Deterministic and Stochastic Analysis of the MUSE-4 Experiments on the Neutronics of Accelerator-Driven Systems
J. F. Lebrat, G. Aliberti, A. D'Angelo, A. Billebaud, R. Brissot, H. Brockmann, M. Carta, C. Destouches, F. Gabrielli, E. Gonzalez, A. Hogenbirk, R. Klein-Meulenkamp, C. Le Brun, E. Liatard, F. Mellier, N. Messaoudi, V. Peluso, M. Plaschy, M. Thomas, D. Villamarín, J. Vollaire
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 49-67
Technical Paper | doi.org/10.13182/NSE05-100
New Evaluation of the 99Tc Neutron-Induced Cross Sections for the ENDF/B-VII.0 Library
D. Rochman, M. Herman, S. F. Mughabghab, P. Oblozinský
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 68-77
Technical Paper | doi.org/10.13182/NSE08-A2739
Theoretical Calculations of n + 232,234,236,238,240U Reaction Cross Sections
Yinlu Han
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 78-87
Technical Paper | doi.org/10.13182/NSE08-A2740
Impact of Antifoam Agent Addition on Hydrogen Formation in the Hanford Waste Treatment and Immobilization Plant
D. J. Sherwood, C. L. Crawford, T. L. White, C. E. Duffey, T. B. Calloway
Nuclear Science and Engineering | Volume 158 | Number 1 | January 2008 | Pages 88-96
Technical Note | doi.org/10.13182/NSE08-A2741
Adjoint Sensitivity Analysis of Dynamic Reliability Models Based on Markov Chains - I: Theory
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 97-113
Technical Paper | doi.org/10.13182/NSE08-A2742
Adjoint Sensitivity Analysis of Dynamic Reliability Models Based on Markov Chains - II: Application to IFMIF Reliability Assessment
Dan G. Cacuci, Iulian Balan, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 114-153
Technical Paper | doi.org/10.13182/NSE08-A2743
Coarse-Mesh Angular Dependent Rebalance Acceleration of the Method of Characteristics in x-y Geometry
Young Ryong Park, Nam Zin Cho
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 154-163
Technical Paper | doi.org/10.13182/NSE06-23
Multifractal Analysis of Chaotic Flashing-Induced Instabilities in Boiling Channels in the Natural-Circulation CIRCUS Facility
Christophe Demazière, Christian Marcel, Martin Rohde, Tim van der Hagen
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 164-193
Technical Paper | doi.org/10.13182/NSE08-A2745
Influence of Secondary Flow Generated in a 90-deg Bend on the Thermal-Hydraulic Characteristics in a Mixing Tee
Kazuhisa Yuki, Yoshimasa Sugawara, Seyed Mohammad Hosseini, Hidetoshi Hashizume, Saburo Toda, Masa-aki Tanaka, Toshiharu Muramatsu
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 194-202
Technical Paper | doi.org/10.13182/NSE08-A2746
Calculation of the Minimum Critical Mass of Fissile Nuclides
Richard Q. Wright, Calvin M. Hopper
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 203-209
Technical Note | doi.org/10.13182/NSE08-A2747
Some Observations on Spontaneous Fission Nuclei
Yigal Ronen
Nuclear Science and Engineering | Volume 158 | Number 2 | February 2008 | Pages 210-212
Letter To the Editor | doi.org/10.13182/NSE08-A2748
Light Water Reactor Equilibrium Cycle Search Methodology for Assembly-Level Fuel Cycle Analysis
Reuben T. Sorensen, John C. Lee
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 213-230
Technical Paper | doi.org/10.13182/NSE08-A2749
A Modeling of BWR-MOX Assemblies Based on the Characteristics Method Combined with Advanced Self-Shielding Models
R. Le Tellier, A. Hébert, A. Santamarina, O. Litaize
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 231-243
Technical Paper | doi.org/10.13182/NSE08-A2750
Self-Adaptive Spherical Wavelets for Angular Discretizations of the Boltzmann Transport Equation
A. G. Buchan, C. C. Pain, M. D. Eaton, R. P. Smedley-Stevenson, A. J. H. Goddard
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 244-263
Technical Paper | doi.org/10.13182/NSE08-A2751
Optimization of Burnable Poison Loading for HTGR Cores with OTTO Refueling
Hoai Nam Tran, Yasuyoshi Kato, Yasushi Muto
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 264-271
Technical Paper | doi.org/10.13182/NSE08-A2752
Absolute Measurement of eff Based on Rossi- Experiments and the Two-Region Model in the IPEN/MB-01 Research Reactor
Renato Yoichi Ribeiro Kuramoto, Adimir dos Santos, Rogario Jerez, Ricardo Diniz
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 272-283
Technical Paper | doi.org/10.13182/NSE06-120
Influence of Coolant Flow Direction on Criticality Waves
Hugo van Dam
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 284-288
Technical Paper | doi.org/10.13182/NSE08-A2754
Implementation of Two-Level Coarse-Mesh Finite Difference Acceleration in an Arbitrary Geometry, Two-Dimensional Discrete Ordinates Transport Method
Zhaopeng Zhong, Thomas J. Downar, Yunlin Xu, Mark D. DeHart, Kevin T. Clarno
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 289-298
Technical Note | doi.org/10.13182/NSE06-24TN
