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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
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Latest News
Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
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Development of a Solidification Model for TEXAS-VI Code and Application to FARO L14 Analysis
R. H. Chen, M. L. Corradini, G. H. Su, S. Z. Qiu
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE12-10
Meta-Analysis Options for Inconsistent Nuclear Measurements
Tom Burr, Brian Williams, Stephen Croft, Morgan White, Ken Hanson
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 15-27
Technical Paper | doi.org/10.13182/NSE11-112
Phase-Space Interpolated Perturbation Theory with Application to Advanced Test Reactor Shim Rotation Automation
Joshua Peterson, Erich Schneider
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 28-42
Technical Paper | doi.org/10.13182/NSE11-49
Determination and Application of Partial Biases in Criticality Safety Validation
Jeremy A. Roberts, Bradley T. Rearden, Paul P. H. Wilson
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 43-57
Technical Paper | doi.org/10.13182/NSE10-109
When Is the Simple Radiotoxicity Approach Useful for Advanced Fuel Cycle System Assessments Given the Existence of Complex Performance Dose Assessments?
Steven J. Piet
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 58-81
Technical Paper | doi.org/10.13182/NSE11-114
Fault Detection in Nuclear Systems Using Sliding Mode Observers
Günyaz Ablay, Tunc Aldemir
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 82-98
Technical Paper | doi.org/10.13182/NSE11-43
Reply to “Comments on ‘Proliferation-Resistant Fuel for CANDU Reactors’”
Yigal Ronen
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 99-99
Letter to the Editor | doi.org/10.13182/NSE12-79L
Comments on “Proliferation-Resistant Fuel for CANDU Reactors”
Jeremy Whitlock
Letter to the Editor | doi.org/10.13182/NSE12-62L
Two Subcell Balance Methods for Solving the Multigroup Discrete Ordinates Transport Equation with Tetrahedral Meshes
Ser Gi Hong
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 101-117
Technical Paper | doi.org/10.13182/NSE11-38
Adjoint-Based Sensitivity Analysis of Coupled Criticality Problems
Zoltán Perkó, Danny Lathouwers, Jan Leen Kloosterman, Tim van der Hagen
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 118-138
Technical Paper | doi.org/10.13182/NSE12-18
Neutron Activation Property of Colemanite-Peridotite Concrete
Koichi Okuno, Hideaki Matsue, Satoru Miyata, Yoshiaki Kiyanagi
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 139-149
Technical Paper | doi.org/10.13182/NSE12-15
Pebble Flow and Coolant Flow Analysis Based on a Fully Coupled Multiphysics Model
Yanheng Li, Wei Ji
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 150-162
Technical Paper | doi.org/10.13182/NSE12-13
Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor During Startup Operations
Tsung-Kuang Yeh, Mei-Ya Wang
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 163-171
Technical Paper | doi.org/10.13182/NSE11-85
Study of Using Zirconium as a Reflector for Light Water Reactors
Nader M. A. Mohamed
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 172-181
Technical Paper | doi.org/10.13182/NSE11-77
Exact Solutions of the Two-Dimensional Cell Problem
M. M. R. Williams
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 182-196
Technical Note | doi.org/10.13182/NSE12-11
High-Fidelity Approximations for Extinction Probability Calculations
Scott D. Ramsey, Gregory J. Hutchens
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 197-205
Technical Note | doi.org/10.13182/NSE11-34
Random Sampling from the Klein-Nishina Distribution: Efficiency, Parsimony, and Speed
Kirk Mathews
Nuclear Science and Engineering | Volume 173 | Number 3 | March 2013 | Pages 207-221
Technical Paper | doi.org/10.13182/NSE11-57
Preconditioned Krylov Solution of Response Matrix Equations
E. E. Lewis, Yunzhao Li, M. A. Smith, W. S. Yang, Allan B. Wollaber
Nuclear Science and Engineering | Volume 173 | Number 3 | March 2013 | Pages 222-232
Technical Paper | doi.org/10.13182/NSE11-106
Using the Cartesian Discrete Ordinates Code DORT for Assembly-Level Calculations
Sebastian Schunert, Yousry Azmy
Nuclear Science and Engineering | Volume 173 | Number 3 | March 2013 | Pages 233-258
Technical Paper | doi.org/10.13182/NSE11-17
A Discrete Maximum Principle for the Implicit Monte Carlo Equations
Allan B. Wollaber, Edward W. Larsen, Jeffery D. Densmore
Nuclear Science and Engineering | Volume 173 | Number 3 | March 2013 | Pages 259-275
Technical Paper | doi.org/10.13182/NSE11-101
Uncertainty Underprediction in Monte Carlo Eigenvalue Calculations
Brenden T. Mervin, Scott W. Mosher, John C. Wagner, G. I. Maldonado
Nuclear Science and Engineering | Volume 173 | Number 3 | March 2013 | Pages 276-292
Technical Paper | doi.org/10.13182/NSE11-104
Optimization of Thermal-Hydraulic Reactor System for SMRs via Data Assimilation and Uncertainty Quantification
Jaeseok Heo, Paul J. Turinsky, J. Michael Doster
Nuclear Science and Engineering | Volume 173 | Number 3 | March 2013 | Pages 293-311
Technical Paper | doi.org/10.13182/NSE11-113
