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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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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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Analysis of Differences in Void Coefficient Predictions for Mixed-Oxide-Fueled Tight-Pitch Light Water Reactor Cells
Hironobu Unesaki, Seiji Shiroya, Keiji Kanda, Stéphane Cathalau, Franck-Olivier Carré, Otohiko Aizawa, Toshikazu Takeda
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE00-A2120
Measurement of Activation Reaction Rate Distributions in a Lead Assembly Bombarded with 500-MeV Protons
Hiroshi Takada, Shin-ichro Meigo, Toshinobu Sasa, Kazufumi Tsujimoto, Hideshi Yasuda
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 23-32
Technical Paper | doi.org/10.13182/NSE00-A2121
Epithermal Inverse Kinetic Measurements and Their Interpretation Using a Two-Group Point-Kinetic Model
Marc Rosselet, Rakesh Chawla, Tony Williams
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 33-47
Technical Paper | doi.org/10.13182/NSE99-33
Influence of the Thermal Cutoff Energy on the Calculation of Neutronic Parameters for Light Water Reactor Lattices
Jean-Marie Paratte, Sandro Pelloni
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 48-56
Technical Paper | doi.org/10.13182/NSE00-A2123
Properties of a Cold-Neutron Irradiation Facility for In Vitro Research on Boron Neutron Capture Therapy at the Geesthacht Neutron Facility
L. Lüdemann, R. Kampmann, W. Sosaat, P. Staron, P. Wille
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 57-63
Technical Paper | doi.org/10.13182/NSE00-A2124
Verification of the Neutron Flux of a Modified Zero-Power Reactor Using a Neutron Activation Method
Lung Kwang Pan, Cheng Si Tsao
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 64-72
Technical Paper | doi.org/10.13182/NSE00-A2125
A Multigroup Albedo Method for Transport Calculations: Application to the Orphée Core
S. Rauck, R. Sanchez, I. Zmijarevic, M. Nobile
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 73-83
Technical Paper | doi.org/10.13182/NSE00-A2126
Nuclide Importance and the Steady-State Burnup Equation
Hiroshi Sekimoto, Atsushi Nemoto
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 84-102
Technical Paper | doi.org/10.13182/NSE00-A2127
Differential Sampling Applied to Mammography Image Simulation
Douglas E. Peplow, Kuruvilla Verghese
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 103-122
Technical Paper | doi.org/10.13182/NSE00-A2128
Neutron Transport in Spatially Random Media: An Assessment of the Accuracy of First Order Smoothing
M. M. R. Williams
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 123-140
Technical Paper | doi.org/10.13182/NSE00-A2129
New High-Resolution Fission Cross-Section Measurements of 233U in the 0.4-eV to 700-keV Energy Range
K. H. Guber, R. R. Spencer, L. C. Leal, J. A. Harvey, N. W. Hill, G. Dos Santos, R. O. Sayer, D. C. Larson
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 141-149
Technical Paper | doi.org/10.13182/NSE00-A2130
Reactivity Control Method for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)
Hangbok Choi, Won Il Ko, Myung Seung Yang
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 150-164
Technical Paper | doi.org/10.13182/NSE00-A2131
SPACON - A Theoretical Model for Calculating the Heat Transport Properties in Sphere-Pac Fuel Pins
F. Botta, C. Hellwig
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 165-176
Technical Paper | doi.org/10.13182/NSE00-A2132
Experimental Study of Two-Phase Flow Oscillation in Natural Circulation
S. Y. Jiang, X. X. Wu, Y. J. Zhang
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 177-189
Technical Paper | doi.org/10.13182/NSE00-A2133
On the Curvature of Transmitted Intensity Plots in Broad Beam Studies
A. H. El-Kateb
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 190-198
Technical Paper | doi.org/10.13182/NSE00-A2134
Spatial and Angular Moment Analysis of Continuous and Discretized Transport Problems
Patrick S. Brantley, Edward W. Larsen
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 199-226
Technical Paper | doi.org/10.13182/NSE00-A2135
Measurement of Absolute Fission Yields in the Fast Neutron-Induced Fission of Actinides: 238U, 237Np, 238Pu, 240Pu, 243Am, and 244Cm by Track-Etch-cum-Gamma Spectrometry
R. H. Iyer, H. Naik, A. K. Pandey, P. C. Kalsi, R. J. Singh, A. Ramaswami, A. G. C. Nair
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 227-245
Technical Paper | doi.org/10.13182/NSE00-A2136
Effects of Differing Energy Dependences in Three Level-Density Models on Calculated Cross Sections
C. Y. Fu
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 246-259
Technical Paper | doi.org/10.13182/NSE00-A2137
16O(n,p)16N Reaction Cross Sections Around 14 MeV
M.Subasi, E. Gültekin, I. A. Reyhancan, Y. Özbir, G. Tarcan, M. Sirin, M. N. Erduran
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 260-266
Technical Paper | doi.org/10.13182/NSE00-A2138
Numerical Simulation of the Emergency Condenser of the SWR-1000
Eckhard Krepper, Andreas Schaffrath, Attila Aszódi
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 267-279
Technical Paper | doi.org/10.13182/NSE00-A2139
Use of Axially Graded Burnable Boron for Hot-Spot Temperature Reduction in a Pressurized Water Reactor Core
M. Segev, A. Galperin, E. Schwageraus
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 280-287
Technical Paper | doi.org/10.13182/NSE00-A2140
Lognormal Size Distribution Theory for Deposition of Polydisperse Aerosol Particles
S. H. Park, K. W. Lee
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 288-295
Technical Note | doi.org/10.13182/NSE00-A2141
Application of a Simple Ramsauer Model for Neutron Total Cross Sections for Nuclear Mass Numbers A < 40
S. M. Grimes, J. D. Anderson, R. W. Bauer
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 296-303
Technical Note | doi.org/10.13182/NSE00-A2142
Calculation of the Dancoff Factor for Pebble Bed Reactors
J. Valko, P. V. Tsvetkov, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 304-307
Technical Note | doi.org/10.13182/NSE00-A2143
