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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
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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Biases in Monte Carlo Eigenvalue Calculations
Ely M. Gelbard, Albert G. Gu
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE94-A13564
Importance Iteration in MORSE Monte Carlo Calculations
J. L. Kloosterman, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 10-21
Technical Paper | doi.org/10.13182/NSE94-A13565
Modeling of Gravity-Driven Oscillatory Countercurrent Two-Phase Channel Flows
S. M. Ghiaasiaan, B. K. Kamboj, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 22-32
Technical Paper | doi.org/10.13182/NSE94-A13566
Thermal and Stability Analysis of a Two-Phase Natural Circulation Loop
Fu-Shin Wang, Lin-Wen Hu, Chin Pan
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 33-46
Technical Paper | doi.org/10.13182/NSE94-A13567
Determination of Point Isotropic Buildup Factors of Gamma Rays Including Incoherent and Coherent Scattering for Aluminum, Iron, Lead, and Water by the Discrete Ordinates Method
S. Kitsos, A. Assad, C. M. Diop, J. C. Nimal, P. Ridoux
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 47-66
Technical Paper | doi.org/10.13182/NSE94-A13568
The 93Nb(n,xp) Reaction at En = 14.6 MeV
Bangjiao Ye, Yangmei Fan, Zhongmin Wang, Rongdian Han, Zhenxi Xiao
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 67-75
Technical Paper | doi.org/10.13182/NSE94-A13569
Powerful Hard-Spectrum Neutrino Source Based on Lithium Converter of Reactor Neutrons to Antineutrinos
Yu. S. Lyutostansky, V. I. Lyashuk
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 77-87
Technical Paper | doi.org/10.13182/NSE94-A20074
Nucleon Double-Differential Cross Section Based on Anisotropic Intranuclear Scattering
Qingbiao Shen, Jingshang Zhang
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 88-98
Technical Paper | doi.org/10.13182/NSE94-A20075
Double-Differential Cross Section of Light Composite Particles in the Exciton Model
Qingbiao Shen
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 99-109
Technical Paper | doi.org/10.13182/NSE93-66
The Use of an Expanded Polynomial Orthogonal Set in Approximations to Gamma-Ray Buildup Factor Data
Ivan Michieli
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 110-120
Technical Paper | doi.org/10.13182/NSE94-A20077
Solution of Depletion Chain Equations Using Nonsingular Bateman Coefficients
Zoran Vukadin
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 121-125
Technical Paper | doi.org/10.13182/NSE94-A20078
Countercurrent Gas-Liquid Flow in a Pressurized Water Reactor Hot Leg
Martin Lopez de Bertodano
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 126-133
Technical Paper | doi.org/10.13182/NSE94-A20079
Impurity Characterization of Si1−xGex Circuit Structures with the Use of Neutron Activation Analysis
S. C. McGuire,T. Z. Hossain, R. J. Soave
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 134-139
Technical Note | doi.org/10.13182/NSE94-A20080
Accounting for the Thermal Neutron Flux Depression in Voluminous Samples for Instrumental Neutron Activation Analysis
R. M. W. Overwater, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 141-157
Technical Paper | doi.org/10.13182/NSE94-A28530
KENO-NR: A Monte Carlo Code for Simulating 252Cf-Source-Driven Noise Measurements to Determine Subcriticality
Edward P. Ficaro, David K. Wehe
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 158-176
Technical Paper | doi.org/10.13182/NSE94-A28531
Robust Wide-Range Control of Nuclear Reactors by Using the Feedforward-Feedback Concept
Chen-Kuo Weng, Robert M. Edwards, Asok Ray
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 177-185
Technical Paper | doi.org/10.13182/NSE94-A28532
Reactivity Surveillance in a Nuclear Reactor by Using a Layered Artificial Neural Network
A. John Arul
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 186-193
Technical Paper | doi.org/10.13182/NSE94-A28533
Fault Diagnosis Via Neural Networks: The Boltzmann Machine
M. Marseguerra, E. Zio
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 194-200
Technical Paper | doi.org/10.13182/NSE94-A28534
Determination of the Double Angular and Energy Differential Gamma-Ray Albedo for Iron Material by Using the Monte Carlo Method
C. M. Diop, B. Elhamzaoui, J. C. Nimal
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 201-226
Technical Paper | doi.org/10.13182/NSE94-A21499
Monte Carlo Calculation of Dancoff Factors in Irregular Geometries
S.Fehér, J. E. Hoogenboom, P. F. A. de Leege, J. Valkó
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE94-A21500
Sensitivity, Uncertainty Assessment, and Target Accuracies Related to Radiotoxicity Evaluation
G. Palmiotti, M. Salvatores, R. N. Hill
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 239-250
Technical Paper | doi.org/10.13182/NSE94-A21501
Photon Interaction Cross Sections of Several Sugars for 137Cs and 60Co Photons
K. P. Gopinathan Nair, T. K. Umesh, Ramakrishna Gowda
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 251-253
Technical Paper | doi.org/10.13182/NSE94-A21502
Reduction of the Sodium Void Reactivity Effect by Using a 99Tc Layer
S.F. Kessler
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 254-258
Technical Note | doi.org/10.13182/NSE94-A21503
