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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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IAEA convoy hit by Russian drone
A drone targeted and damaged an official vehicle of the International Atomic Energy Agency on December 10 as it traveled toward the front line in eastern Ukraine during a rotation of IAEA teams at Ukraine’s Zaporizhzhia nuclear power plant (ZNPP). In a video message, IAEA director general Rafael Mariano Grossi condemned the strike as an “unacceptable” attack on IAEA staff working to prevent a nuclear accident during a military conflict.
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Extremely Accurate Sequential Verification of RELAP5-3D
G. L. Mesina, D. L. Aumiller, F. X. Buschman
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 1-12
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-151
Standardized Consolidated Calculated and Reference Experimental Database (SCCRED): A Supporting Tool for V&V and Uncertainty Evaluation of Best-Estimate System Codes for Licensing Applications
A. Petruzzi, F. D'Auria
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 13-53
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE15-79
Hyperbolicity Criteria for System of Field Equations of One-Dimensional Two-Phase Flow with Compressible Components
Igor Arshavsky
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 54-70
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-144
Development of Governing Equations Based on Six Fields for the RELAP Code
Glenn A. Roth, Fatih Aydogan
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 71-82
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-149
Modeling Moving Systems with RELAP5-3D
G. L. Mesina, D. L. Aumiller, F. X. Buschman, M. R. Kyle
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 83-95
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE15-3
Implementation and Assessment of Moody Homogeneous Equilibrium Critical Flow Model of RELAP5-3D
Liang-Che Dai, Chung-Yu Yang, Yng-Ruey Yuann, Bau-Shei Pei, Chun-Kuan Shih
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 96-103
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-145
New Simulation Schemes and Capabilities for the PHISICS/RELAP5-3D Coupled Suite
C. Rabiti, A. Alfonsi, A. Epiney
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 104-118
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-143
Qualitative and Quantitative Evaluation of Coupling Approaches for Coupling of RELAP5 and LabVIEW
Zheng Fu, Joshua Pack, Fatih Aydogan
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 119-134
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE15-4
Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2
G. Noguere, D. Bernard, P. Blaise, O. Bouland, L. Leal, P. Leconte, O. Litaize, Y. Peneliau, B. Roque, A. Santamarina, J.-F. Vidal
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 135-150
Technical Paper | doi.org/10.13182/NSE15-9
A Linear Source Approximation Scheme for the Method of Characteristics
Rodolfo M. Ferrer, Joel D. Rhodes III
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 151-165
Technical Paper | doi.org/10.13182/NSE15-6
Development and Evaluation of High-Fidelity Product and Evenly Spaced Angular Quadratures for Three-Dimensional Discrete Ordinates Calculations with Large Air Regions
Daniel B. Fromowitz, Gary B. Zeigler
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 166-180
Technical Paper | doi.org/10.13182/NSE14-49
Fission and Surface Source Iteration Method for Domain Decomposed Monte Carlo Whole-Core Calculation
YuGwon Jo, Nam Zin Cho
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 181-196
Technical Paper | doi.org/10.13182/NSE14-150
Design Space Analysis for Breed-and-Burn Reactor Cores
Staffan Qvist, Ehud Greenspan
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 197-212
Technical Paper | doi.org/10.13182/NSE14-135
Developments in Core-Barrel Motion Monitoring and Applications to the Ringhals PWR Units
Imre Pázsit, Cristina Montalvo, Henrik Nylén, Tell Andersson, Augusto Hernández-Solís, Petty Bernitt Cartemo
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 213-227
Technical Paper | doi.org/10.13182/NSE15-14
Online Monitoring and Prognostics for Passive Components in Nuclear Power Plants
Pradeep Ramuhalli, Surajit Roy, Jangbom Chai
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 228-242
Technical Paper | doi.org/10.13182/NSE14-127
Quantifying 3-D Positional Uncertainty of Radiological Material from Nuclear Detonation Videos
Daniel T. Schmitt, Robert Slaughter, Gilbert L. Peterson
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 243-255
Technical Paper | doi.org/10.13182/NSE14-141
Neutron Emission Spectra of Triton Beams of 20.22-MeV Fully Stopped in Targets of H2O, D2O, LiF, Si, Ni, Mo, Ta, W, Pt, and Au
M. Drosg, D. M. Drake
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 256-260
Technical Note | doi.org/10.13182/NSE15-17
Effects and Modeling of Power History in Thorium-Based Fuels in Pressure-Tube Heavy Water Reactors
Blair P. Bromley, Geoffrey W. R. Edwards, Pranavan Sambavalingam
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 263-286
Technical Paper | doi.org/10.13182/NSE15-19
Mesh-Free Simulation of Aerosol Evolution
Shawn A. Campbell, John Palsmeier, Sudarshan K. Loyalka
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 287-296
Technical Paper | doi.org/10.13182/NSE15-40
Higher-Order Chebyshev Rational Approximation Method and Application to Burnup Equations
Maria Pusa
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 297-318
Technical Paper | doi.org/10.13182/NSE15-26
Hydrodynamically Developing and Fully Developed Laminar Flows in a Semicircular Duct: Analytical and Computational Analyses
Sai K. Mylavarapu, Xiaodong Sun, Richard N. Christensen
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 319-331
Technical Paper | doi.org/10.13182/NSE14-107
SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations
Christopher M. Perfetti, Bradley T. Rearden, William R. Martin
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 332-353
Technical Paper | doi.org/10.13182/NSE15-12
Development of a Generalized Perturbation Theory Method for Sensitivity Analysis Using Continuous-Energy Monte Carlo Methods
Christopher M. Perfetti, Bradley T. Rearden
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 354-368
Technical Paper | doi.org/10.13182/NSE15-13
An Implicit Correlation Method for COMET Core Eigenvalue Uncertainty Analysis
Dingkang Zhang, Farzad Rahnema
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 369-376
Technical Paper | doi.org/10.13182/NSE15-15
The Use of Nuclear Data as Nuisance Parameters in the Integral Data Assimilation of the PROFIL Experiments
E. Privas, P. Archier, C. De Saint Jean, G. Noguere, J. Tommasi
Nuclear Science and Engineering | Volume 182 | Number 3 | March 2016 | Pages 377-393
Technical Paper | doi.org/10.13182/NSE15-21
The Collision Probability Method in Today’s Computer Environment
Dimitar Altiparmakov, Robert Wiersma
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 395-416
Technical Paper | doi.org/10.13182/NSE15-28
Discrete Ordinates Method for the Transport Equation Preserving One-Dimensional Spherical Symmetry in Two-Dimensional Cylindrical Geometry
F. Chaland, G. Samba
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 417-434
Technical Paper | doi.org/10.13182/NSE15-38
A Multilevel Quasi-Static Kinetics Method for Pin-Resolved Transport Transient Reactor Analysis
Ang Zhu, Yunlin Xu, Thomas Downar
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 435-451
Technical Paper | doi.org/10.13182/NSE15-39
A Heat Conduction and Convection Analytical Benchmark for Adjoint Solution Verification of Computational Fluid Dynamics Codes Used in Reactor Design
Dan G. Cacuci, Ruixian Fang, Milica Ilic, Madalina C. Badea
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 452-480
Technical Paper | doi.org/10.13182/NSE15-69
Neutron Multiplicity Counting: Credible Regions for Reconstruction Parameters
Jérôme M. Verbeke
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 481-501
Technical Paper | doi.org/10.13182/NSE15-35
Nuclear Fuel Cycle Transition Analysis Under Uncertainty
U. B. Phathanapirom, E. A. Schneider
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 502-522
Technical Paper | doi.org/10.13182/NSE15-25
Accident-Tolerant-Fuel Performance Analysis of APMT Steel Clad/UO2 Fuel and APMT Steel Clad/UN-U3Si5 Fuel Concepts
Jack Galloway, Cetin Unal
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 523-537
Technical Paper | doi.org/10.13182/NSE15-7
CriSAA: A Simulation Code for Evaluation of Criticality Transients Involving Low Source Start-Up
Jun-Yun Yang, Xiao Gang, Yang-Jun Ying
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 538-554
Technical Paper | doi.org/10.13182/NSE15-44
Uniform Tally Density–Based Strategy for Efficient Global Tallying in Monte Carlo Criticality Calculation
Danhua ShangGuan, Gang Li, Baoyin Zhang, Li Deng, Yan Ma, Yuanguan Fu, Rui Li,Xiaoli Hu
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 555-562
Technical Paper | doi.org/10.13182/NSE15-32
Estimation of Double-Differential Angle-Dependent Neutron Production Cross Sections from Tritons on 197Au at Energies from 5.97 to 19.14 MeV
Manfred Drosg, Bernard Hoop
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 563-570
Technical Note | doi.org/10.13182/NSE15-57
