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Division Spotlight
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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February 2025
Nuclear Technology
January 2025
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Latest News
Senate committee hears from energy secretary nominee Chris Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Development of Methods for Calculation of Deuteron-Lithium and Neutron-Lithium Cross Sections for Energies up to 50 MeV
A. Yu. Konobeyev, Yu. A. Korovin, P. E. Pereslavtsev, Ulrich Fischer, Ulrich von Möllendorff
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 1-23
Technical Paper | doi.org/10.13182/NSE00-31
Threshold Reaction Cross Sections of Nickel Isotopes, Averaged Over a 235U Fission Neutron Spectrum
M. A. Arribére, S. Ribeiro Guevara, P. M. Suárez, A. J. Kestelman
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 24-32
Technical Paper | doi.org/10.13182/NSE01-A2219
Nonnegative Anisotropic Group Cross Sections: A Hybrid Monte Carlo-Discrete Elements-Discrete Ordinates Approach
J. Mark DelGrande, Kirk A. Mathews
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 33-46
Technical Paper | doi.org/10.13182/NSE00-69
A Transport Condensed History Algorithm for Electron Monte Carlo Simulations
Danny R. Tolar, Jr., Edward W. Larsen
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 47-65
Technical Paper | doi.org/10.13182/NSE01-A2221
Neutron Transport in Spatially Random Media: Eigenvalue Problems
M. M. R. Williams, Edward W. Larsen
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE01-A2222
A Spatial Kinetics Method Ensuring Neutronic Balance with Thermal-Hydraulic Feedback and Its Application to a Main Steam Line Break
Yoshiro Asahi, Keisuke Okumura, Yasuo Ose
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 78-95
Technical Paper | doi.org/10.13182/NSE01-A2223
Genetic Algorithms for Estimating Effective Parameters in a Lumped Reactor Model for Reactivity Predictions
Marzio Marseguerra, Enrico Zio
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 96-104
Technical Paper | doi.org/10.13182/NSE01-A2224
An Alternate Formulation of the Nodal Expansion Method
Keqiang Ruan, Xiaogang Xue, Xuedong Fu
Nuclear Science and Engineering | Volume 139 | Number 1 | September 2001 | Pages 105-110
Technical Note | doi.org/10.13182/NSE01-A2225
High-Resolution Transmission Measurements of 233U Using a Cooled Sample at the Temperature T = 11 K
K. H. Guber, R. R. Spencer, L. C. Leal, P. E. Koehler, J. A. Harvey, R. O. Sayer, H. Derrien, T. E. Valentine, D. E. Pierce, V. M. Cauley, T. A. Lewis
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 111-117
Technical Paper | doi.org/10.13182/NSE01-A2226
Conceptual Design of a Fluidized Bed Nuclear Reactor
J. L. Kloosterman, V. V. Golovko, H. van Dam, T. H. J. J. van der Hagen
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 118-137
Technical Paper | doi.org/10.13182/NSE01-A2227
Conceptual Neutronic Design of a Lead-Bismuth-Cooled Actinide Burning Reactor
Pavel Hejzlar, Michael J. Driscoll, Mujid S. Kazimi
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 138-155
Technical Paper | doi.org/10.13182/NSE01-A2228
The Analytic Function Expansion Nodal Method Refined with Transverse Gradient Basis Functions and Interface Flux Moments
Sweng Woong Woo, Nam Zin Cho, Jae Man Noh
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 156-173
Technical Paper | doi.org/10.13182/NSE01-A2229
Numerical Optimization of Computing Algorithms of the Variational Nodal Method Based on Transformation of Variables
W. S. Yang, G. Palmiotti, E. E. Lewis
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 174-185
Technical Paper | doi.org/10.13182/NSE01-A2230
Analytic Radiation Transport Systems and Monte Carlo Benchmarks
S. N. Cramer
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 186-208
Technical Paper | doi.org/10.13182/NSE01-A2231
Measurement of Neutron and Gamma-Ray Absorbed Doses Under Criticality Accident Conditions at TRACY Using Tissue-Equivalent Dosimeters
Hiroki Sono, Hiroshi Yanagisawa, Akio Ohno, Takuji Kojima, Noboru Soramasu
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 209-220
Technical Paper | doi.org/10.13182/NSE01-A2232
An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors
Tsung-Kuang Yeh, Fang Chu
Nuclear Science and Engineering | Volume 139 | Number 2 | October 2001 | Pages 221-233
Technical Paper | doi.org/10.13182/NSE00-77
FORMOSA-P Three-Dimensional/Two-Dimensional Geometry Collapse Methodology
Paul M. Keller, Paul J. Turinsky
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 235-247
Technical Paper | doi.org/10.13182/NSE01-A2234
A Time-Dependent, Three-Dimensional Neutron Transport Methodology
Sedat Goluoglu, H. L. Dodds
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 248-261
Technical Paper | doi.org/10.13182/NSE01-A2235
LWR-PROTEUS Verification of Reaction Rate Distributions in Modern 10 × 10 Boiling Water Reactor Fuel
F. Jatuff, P. Grimm, O. Joneja, M. Murphy, A. Lüthi, R. Seiler, R. Brogli, R. Jacot-Guillarmod, T. Williams, S. Helmersson, R. Chawla
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 262-272
Technical Paper | doi.org/10.13182/NSE01-A2236
Measurement of Neutron-Induced Fission Cross Sections of 229Th and 231Pa Using Linac-Driven Lead Slowing-Down Spectrometer
Katsuhei Kobayashi, Shuji Yamamoto, Samyol Lee, Hyun-Je Cho, Hajimu Yamana, Hirotake Moriyama, Yoshiaki Fujita, Toshiaki Mitsugashira
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 273-281
Technical Paper | doi.org/10.13182/NSE01-A2237
Neutron Radiative Capture Cross Section of 232Th in the Energy Range from 0.06 to 2 MeV
D. Karamanis, M. Petit, S. Andriamonje, G. Barreau, M. Bercion, A. Billebaud, B. Blank, S. Czajkowski, R. Del Moral, J. Giovinazzo, V. Lacoste, C. Marchand, L. Perrot, M. Pravikoff, J. C. Thomas
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 282-292
Technical Paper | doi.org/10.13182/NSE01-A2238
An Efficient Formulation of the Modified Nodal Integral Method and Application to the Two-Dimensional Burgers' Equation
Bradley L. Wescott, Rizwan-uddin
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 293-305
Technical Paper | doi.org/10.13182/NSE01-A2239
CANDLE: The New Burnup Strategy
Hiroshi Sekimoto, Kouichi Ryu, Yoshikane Yoshimura
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 306-317
Technical Note | doi.org/10.13182/NSE01-01
Study of Properties of the Neutron Production Target Induced from 150-MeV Incident Proton Energy for the China ADS
S. Fan, Y. Ye, Z. Zhao, H. Yu, Z. Luo
Nuclear Science and Engineering | Volume 139 | Number 3 | November 2001 | Pages 318-326
Technical Note | doi.org/10.13182/NSE01-A2241
