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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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Numerical Caseology by Lagrange Interpolation for the 1D Neutron Transport Equation in a Slab
B. D. Ganapol
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 1-13
Technical Paper | doi.org/10.1080/00295639.2022.2097494
Uncertainty Quantification of a Light Water Pulsed-Neutron Die-Away Experiment to Thermal Neutron Scattering Laws
Daniel Siefman, Mathieu Hursin, Catherine Percher, David Heinrichs
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 14-24
Technical Paper | doi.org/10.1080/00295639.2022.2103344
Post-Neutron Fission Product Yield Distribution in the Spontaneous Fission of 244Cm
H. Naik, R. J. Singh, W. Jang
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 25-44
Technical Paper | doi.org/10.1080/00295639.2022.2103345
An Analysis of Transport Effects in Steady-State Simulation of the Molten Salt Reactor Experiment
Aaron J. Reynolds, Todd S. Palmer
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 45-73
Technical Paper | doi.org/10.1080/00295639.2022.2097565
Comparisons of Supercritical Loop Flow and Heat Transfer Behavior Under Uniform and Nonuniform High-Flux Heat Inputs
Dong Yang, Lin Chen, Yongchang Feng, Haisheng Chen
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 74-91
Technical Paper | doi.org/10.1080/00295639.2022.2102391
Development of an Activity Transport Model and In Situ Measurements on Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan Nuclear Power Plant
Yu-Hung Shih, Mei-Ya Wang, Tsuey-Lin Tsai, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 92-103
Technical Paper | doi.org/10.1080/00295639.2022.2102392
Infiltration and Evaporation in Multiplying Porous Media and Associated Criticality Phenomena
M. M. R. Williams
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 104-131
Technical Paper | doi.org/10.1080/00295639.2022.2103336
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study
M. Chandra Kumar, A. Jasmin Sudha, V. Subramanian, S. Athmalingam, B. Venkatraman
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 132-143
Technical Paper | doi.org/10.1080/00295639.2022.2103338
Asymptotic Diffusion Limits of the Multigroup Neutron Transport Equations
Edward W. Larsen
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 145-163
Technical Paper | doi.org/10.1080/00295639.2022.2058847
Toward a More Realistic Analysis of Neutron Clustering
Thomas M. Sutton
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 164-175
Technical Paper | doi.org/10.1080/00295639.2022.2065872
Theoretical Derivation of a Unique Combination Number Hidden in the Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation
Tomohiro Endo, Fuga Nishioka, Akio Yamamoto, Kenichi Watanabe, Cheol Ho Pyeon
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 176-188
Technical Paper | doi.org/10.1080/00295639.2022.2049992
A Stochastic Transport Model for the Cumulative Number of Fissions and Deposited Fission Energy
Anil K. Prinja, Patrick F. O’Rourke
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 189-211
Technical Paper | doi.org/10.1080/00295639.2022.2087830
A Limited-Memory Framework for Conditional Point Sampling for Radiation Transport in 1D Stochastic Media
Emily H. Vu, Aaron J. Olson
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 212-232
Technical Paper | doi.org/10.1080/00295639.2022.2116378
Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators
Patrick Behne, Jan Vermaak, Jean Ragusa
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 233-261
Technical Paper | doi.org/10.1080/00295639.2022.2112901
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems
Nickolas J. Adamowicz, Annalisa Manera, Edward W. Larsen
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 262-278
Technical Paper | doi.org/10.1080/00295639.2022.2112900
Frequency Transform Method for Transient Analysis of Nuclear Reactors in Monte Carlo
Miriam A. Kreher, Samuel Shaner, Benoit Forget, Kord Smith
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 279-290
Technical Paper | doi.org/10.1080/00295639.2022.2067739
The Legendre Polynomial Axial Expansion Method
Nicholas F. Herring, Benjamin S. Collins, Thomas J. Downar, Aaron M. Graham
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 291-307
Technical Paper | doi.org/10.1080/00295639.2022.2082231
A Multigroup Homogeneous Flux Reconstruction Method Based on the ANOVA-HDMR Decomposition
Pavel M. Bokov, Danniell Botes, Rian H. Prinsloo, Djordje I. Tomašević
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 308-332
Technical Paper | doi.org/10.1080/00295639.2022.2108654
Spatially Dependent Resonance Self-Shielding in CASMO5
Rodolfo M. Ferrer, Joshua M. Hykes
Nuclear Science and Engineering | Volume 197 | Number 2 | February 2023 | Pages 333-350
Technical Paper | doi.org/10.1080/00295639.2022.2053491
Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding System by Laser Heating
L. Soldi, D. Manara, D. Bottomley, D. Robba, L. Luzzi, R. J. M. Konings
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 351-363
Technical Paper | doi.org/10.1080/00295639.2022.2106731
Monte Carlo Source Convergence Acceleration by Hybrid Multigroup and Continuous Energy Neutron Transport
Valeria Raffuzzi, Eugene Shwageraus, Lee Morgan, Paul Cosgrove
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 364-380
Technical Paper | doi.org/10.1080/00295639.2022.2107262
Identifying Thermodynamic Mechanisms Affecting Reactor Pressure Vessel Integrity During Severe Nuclear Accidents Simulated by Laser Heating at the Laboratory Scale
Michail Athanasakis-Kaklamanakis, Dario Manara, Luka Vlahovic, Davide Robba, Konstantinos Boboridis, Markus Ernstberger, Rachel Eloirdi, Pedro Amador, Rudy J. M. Konings
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 381-397
Technical Paper | doi.org/10.1080/00295639.2022.2108643
A CFD Modeling Coupled with VOF Method and Solidification Model for Molten Jet Breakup at Low Velocity
Tao Liu, Yuan Zhou, Mingjun Zhong, Houjun Gong
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 398-412
Technical Paper | doi.org/10.1080/00295639.2022.2116379
Computational Analysis of Thermal Striping in Primary Sodium System of Liquid Metal Fast Breeder Reactor Using Finite Volume Method
S. Suyambazhahan, T. Sundararajan, Sarit K. Das
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 413-427
Technical Paper | doi.org/10.1080/00295639.2022.2116380
Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow
Zhipeng Feng, Fenggang Zang, Shuai Liu, Huanhuan Qi, Xuan Huang
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 428-442
Technical Paper | doi.org/10.1080/00295639.2022.2118478
Improvements in Antineutrino Spectrum by Including Fission Product Corrections and Calculation of Scatter-Based Pulse Height Distributions
Wei Eng Ang, Sanghun Lee, Shikha Prasad
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 443-462
Technical Paper | doi.org/10.1080/00295639.2022.2103348
Methods for Calculating Neutron Transfer Probabilities Between Assemblies
Patrick F. O’Rourke, Anil K. Prinja
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 463-471
Technical Note | doi.org/10.1080/00295639.2022.2106728
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation
Qingming He, Chao Fang, Liangzhi Cao, Haoyu Zhang
Nuclear Science and Engineering | Volume 197 | Number 3 | March 2023 | Pages 472-484
Technical Note | doi.org/10.1080/00295639.2022.2106733
Post-Neutron Mass Yield Distribution in the Thermal Neutron–Induced Fission of 235U
H. Naik, S. P. Dange, R. J. Singh, W. Jang
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 485-509
Technical Paper | doi.org/10.1080/00295639.2022.2133947
Measurements of the 27Al(α,n) Thick Target Yield near Threshold
K. Brandenburg, G. Hamad, Z. Meisel, C. R. Brune, D. E. Carter, J. Derkin, D. C. Ingram, Y. Jones-Alberty, B. Kenady, T. N. Massey, M. Saxena, D. Soltesz, S. K. Subedi, J. Warren
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 510-516
Technical Paper | doi.org/10.1080/00295639.2022.2118483
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems
Anthony P. Barbu, Marvin L. Adams
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 517-533
Technical Paper | doi.org/10.1080/00295639.2022.2123205
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations
Hunter Belanger, Davide Mancusi, Amélie Rouchon, Andrea Zoia
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 534-557
Technical Paper | doi.org/10.1080/00295639.2022.2126719
Introduction of the Adding and Doubling Method for Solving Bateman Equations for Nuclear Fuel Depletion
Olin W. Calvin, Barry D. Ganapol, R. A. Borrelli
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 558-588
Technical Paper | doi.org/10.1080/00295639.2022.2129950
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis
Shuangbao Shu, Ziqiao Yu, Jiaxin Zhang, Zhiqiang Chen, Huajun Liang, Jingjing Chen
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 589-600
Technical Paper | doi.org/10.1080/00295639.2022.2132101
Physics-Informed Neural Network Method and Application to Nuclear Reactor Calculations: A Pilot Study
Mohamed H. Elhareef, Zeyun Wu
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 601-622
Technical Paper | doi.org/10.1080/00295639.2022.2123211
Investigation of the Inhomogeneous Mechanical and Crack Driving Force of Low Alloy Steel SA508 and Its Welded 309L/308L Stainless Steel Cladding
Shuai Wang, He Xue, Guiyi Wu, Zheng Wang, Kuan Zhao, Chenqiang Ni
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 623-632
Technical Paper | doi.org/10.1080/00295639.2022.2123210
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts
Lance Davis, Ralph Hania, Dennis Boomstra, Dillon Rossouw, Florence Charpin-Jacobs, Jan Uhlir, Martin Maracek, Helmut Beckers, Sebastian Riedel
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 633-646
Technical Paper | doi.org/10.1080/00295639.2022.2129951
Effects of Vent Size and Wind on Dispersion of Hydrogen Leaked in a Partially Open Space: Studies by Numerical Analysis
Atsuhiko Terada, Ryuji Nagaishi
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 647-659
Technical Paper | doi.org/10.1080/00295639.2022.2126689
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies
Shifa Wu, Jiashuang Wan, Zhi Chen, Longtao Liao, Kai Xiao, Pengfei Wang
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 660-675
Technical Paper | doi.org/10.1080/00295639.2022.2123204
Mixcoatl Software (Part 1): Coupled Thermal Physics and Mechanics for Efficient Engineering Design
Ross Pivovar, Rebecca Owston
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 676-685
Computer Code Abstract | doi.org/10.1080/00295639.2022.2154114
Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled to 3D FEM Thermal Diffusion Models
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 686-702
Computer Code Abstract | doi.org/10.1080/00295639.2022.2126718
Analysis of Integral Experiment of the AHWR Critical Facility with Diffusion-Based Monte Carlo Method
Argala Srivastava, Deep Bhandari, K. P. Singh, Umasankari Kannan
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 703-710
Technical Note | doi.org/10.1080/00295639.2022.2131343
Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor with Nitride Fuel and Sodium Coolant
Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 711-718
Technical Note | doi.org/10.1080/00295639.2022.2129952
A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications
Scott Wahlquist, Joshua Hansel, Piyush Sabharwall, Amir Ali
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 719-752
Critical Review | doi.org/10.1080/00295639.2022.2082230
Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature Heat Pipe Test Facility
Ilyas Yilgor, Eymon Lan, Shanbin Shi
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 753-770
Technical Paper | doi.org/10.1080/00295639.2022.2087835
Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium Cartridge Loop in Versatile Test Reactor
Zhengting Quan, Adam Dix, Ran Kong, Seungjin Kim, Mamoru Ishii, Mitchell T. Farmer
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 771-787
Technical Paper | doi.org/10.1080/00295639.2022.2082232
Flow-Induced Vibration of Solitary Wire-Wrapped Cylinders in Axial Flow
Chad A. Nixon, Wade R. Marcum
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 788-812
Technical Paper | doi.org/10.1080/00295639.2022.2058846
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)
Haihua Zhao, Lambert Fick, Alexander Heald, Quan Zhou, Samuel Richesson, Noah Sutton, Brandon Haugh
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 813-839
Technical Paper | doi.org/10.1080/00295639.2022.2106724
Simulation of the High Temperature Test Facility (HTTF) Core Using the 2D Ring Model with SAM
Zhiee Jhia Ooi, Thanh Hua, Ling Zou, Rui Hu
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 840-867
Technical Paper | doi.org/10.1080/00295639.2022.2106726
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors
Yeongshin Jeong, Koroush Shirvan, Michael Buric
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 868-885
Technical Paper | doi.org/10.1080/00295639.2022.2102388
Simulation of the Axial-Flow Centrifugal Bubble Separator for Liquid-Fueled Molten Salt Reactors Using Eulerian Two-Fluid Model
Jiaqi Chen, Caleb S. Brooks
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 886-906
Technical Paper | doi.org/10.1080/00295639.2022.2103347
Numerical Investigations of Molten Salt Pump Journal Bearings Under Hydrodynamic Lubrication Conditions for FHRs
Yuqi Liu, Shuai Che, Adam Burak, Daniel L. Barth, Nicolas Zweibaum, Minghui Chen
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 907-919
Technical Paper | doi.org/10.1080/00295639.2022.2103343
Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural Circulation Loop
Sheng Zhang, Hsun-Chia Lin, Xiaodong Sun
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 920-946
Technical Paper | doi.org/10.1080/00295639.2022.2102389
Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of Machine Learning Models
Mahmoud Yaseen, Xu Wu
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 947-966
Technical Paper | doi.org/10.1080/00295639.2022.2123203
Validation and Uncertainty Quantification of Transient Reflood Models Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT Benchmark
Yue Jin, Stephen M. Bajorek, Fan-Bill Cheung
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 967-986
Technical Paper | doi.org/10.1080/00295639.2022.2087834
Scaling, Passive Systems, and the AP-1000
F. D’Auria
Nuclear Science and Engineering | Volume 197 | Number 5 | May 2023 | Pages 987-999
Technical Paper | doi.org/10.1080/00295639.2023.2178874
Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble Bed Nuclear Reactors
Rahman S. Almusafir, Ahmed A. Jasim, Muthanna H. Al-Dahhan
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1001-1037
Critical Review | doi.org/10.1080/00295639.2022.2146993
Numerical Simulation of Subcooled Flow Boiling in a Vertical Annulus Channel Under Near Atmospheric Pressure Conditions
Sachin Tom, P. Mangarjuna Rao, B. Venkatraman, S. Raghupathy
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1038-1070
Technical Paper | doi.org/10.1080/00295639.2022.2133948
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)
Muhammad Ishaq, Muhammad Ilyas, Alam Nawaz Khan Wardag, Muhammad Zaman, Mansoor H. Inayat
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1071-1099
Technical Paper | doi.org/10.1080/00295639.2022.2139565
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box
N. L. Scuro, G. Angelo, E. Angelo, M. H. A. Piro, P. E. Umbehaun, W. M. Torres, D. A. Andrade
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1100-1116
Technical Paper | doi.org/10.1080/00295639.2022.2142437
Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC
Cheng Peng, Youya Song, Jian Deng, Sen Mao, Jiang Wu
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1117-1132
Technical Paper | doi.org/10.1080/00295639.2022.2143208
Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced Fission of 233U
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1133-1158
Technical Paper | doi.org/10.1080/00295639.2022.2142433
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations
Sam Pasmann, Ilham Variansyah, C. T. Kelley, Ryan McClarren
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1159-1173
Technical Paper | doi.org/10.1080/00295639.2022.2143704
High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics
Kaijie Zhu, Boran Kong, Han Zhang, Jiong Guo, Fu Li
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1174-1196
Technical Paper | doi.org/10.1080/00295639.2022.2143706
A Novel Core Design with Movable Moderator for a Fluoride Salt–Cooled High-Temperature Reactor
Zuolong Zhu, Dean Wang, Valmor de Almeida, Charles Forsberg, Eugene Shwageraus
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1197-1212
Technical Paper | doi.org/10.1080/00295639.2022.2146436
Demonstrating Computational Equivalence Between Continuous and Discrete Adjoint Methods by Calculating Time-Dependent Adjoint Solutions with Neutron Diffusion Models
Zeyun Wu, Cihang Lu, Tao Liu
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1213-1238
Technical Paper | doi.org/10.1080/00295639.2022.2143207
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation
Derjew Ayele Ejigu, Xiaojing Liu
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1239-1254
Technical Paper | doi.org/10.1080/00295639.2022.2138688
Wigner-Wilkins Neutron/Nucleus Scattering Kernel Quantum Mechanically Derived
J. A. Grzesik
Nuclear Science and Engineering | Volume 197 | Number 6 | June 2023 | Pages 1255-1263
Technical Note | doi.org/10.1080/00295639.2022.2138064
State-of-the-Art in Evaluation Approaches for Risk Assessment of Insider Threats to Nuclear Facility Physical Protection Systems
Chris Faucett, Karen Vierow Kirkland
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S1-S12
Critical Review | doi.org/10.1080/00295639.2022.2130635
Computing Physical Security System Effectiveness at Commercial Reactors
Matthew Talbot, Dan McCorquodale, Ian Broglie
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S13-S23
Technical Paper | doi.org/10.1080/00295639.2022.2120315
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants
Robby Christian, Vaibhav Yadav, R. Steven Prescott, Shawn W. St. Germain
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S24-S44
Technical Paper | doi.org/10.1080/00295639.2022.2112899
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees
Brian Cohn, Todd Noel, Jeffrey Cardoni, Troy Haskin, Douglas Osborn, Tunc Aldemir
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S45-S56
Technical Paper | doi.org/10.1080/00295639.2023.2177076
Performance Testing of Person Passable Openings to Evaluate Accepted Risk
W. Gary Rivera, Emily Sandt
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S57-S69
Technical Paper | doi.org/10.1080/00295639.2022.2106738
New Security Concepts for Advanced Reactors
Alan Evans, John L. Russell, Benjamin B. Cipiti
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S70-S79
Technical Paper | doi.org/10.1080/00295639.2022.2112134
Possible Does Not Mean Useful: The Role of Probability of Attack in Security Risk Management
Gregory D. Wyss, Adam D. Williams
Nuclear Science and Engineering | Volume 197 | Number 1S | June 2023 | Pages S80-S94
Technical Paper | doi.org/10.1080/00295639.2022.2129224
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 229Th
H. Naik, R. J. Singh, S. P. Dange, W. Jang
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1265-1278
Technical Paper | doi.org/10.1080/00295639.2022.2150029
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 245Cm
H. Naik, R. J. Singh, W. Jang, S. P. Dange
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1279-1292
Technical Paper | doi.org/10.1080/00295639.2022.2153577
141Pr(α,x): New Cross-Section Data With Special Reference to 140Nd Production for Medicine
Ekaterina Sergeevna Kormazeva, Anastasia Romanovna Kulakova, Vladimir Ilyich Novikov, Ramiz Avtandilovich Aliev
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1293-1304
Technical Paper | doi.org/10.1080/00295639.2022.2162303
Uncertainty Propagation in UAM Time-Dependent Neutronics PWR Studies
M. D. Tucker, D. R. Novog
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1305-1330
Technical Paper | doi.org/10.1080/00295639.2022.2160612
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook
Theresa Cutler, Kelsey Amundson, Jesson Hutchinson, Nick Thompson
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1331-1355
Technical Paper | doi.org/10.1080/00295639.2022.2159293
An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part III: Uncertainty Propagation and Multigroup Covariance Matrices
Ketaki Joshi, Nicholas Branam, Isaac Meyer, Ben Forget, Abdulla Alhajri, Vladimir Sobes
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1356-1363
Technical Paper | doi.org/10.1080/00295639.2022.2159268
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method
Qicang Shen, Brendan Kochunas
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1364-1385
Technical Paper | doi.org/10.1080/00295639.2022.2159276
Multigroup Neutron Transport Using a Collision-Based Hybrid Method
Ben Whewell, Ryan G. McClarren, Cory D. Hauck, Minwoo Shin
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1386-1405
Technical Paper | doi.org/10.1080/00295639.2022.2154119
Deep Learning for Multigroup Cross-Section Representation in Two-Step Core Calculations
Nicolas Martin, Zachary Prince, Vincent Labouré, Mauricio Tano-Retamales
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1406-1435
Technical Paper | doi.org/10.1080/00295639.2022.2159220
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head
Hao Yang, Bin Zhang, Pengcheng Gao, Runze Zhai, Jianqiang Shan
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1436-1453
Technical Paper | doi.org/10.1080/00295639.2022.2158676
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation
Chenghui Wan, Wenchang Dong, Lin Guo, Jiahe Bai
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1454-1466
Technical Paper | doi.org/10.1080/00295639.2022.2158704
Thermal-Hydraulic Analysis of the AFIP-7 Irradiation Test in the Advanced Test Reactor—Oxide Growth Prediction and Correlation
Changhu Xing, Casey J. Jesse, Warren F. Jones, Maxine P. Johnson, Ann Marie Phillips, Theron D. Marshall
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1467-1478
Technical Paper | doi.org/10.1080/00295639.2022.2153599
Compensated Feedwater Pump Control Analysis of Effect of Baseload Electricity Demand Reduction on Nuclear Steam Supply System
Frederick Agyemang, Stephen Yamoah, Seth Kofi Debrah
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1479-1490
Technical Paper | doi.org/10.1080/00295639.2022.2132102
Generation IV Nuclear Reactor: Coolant Materials in the Supercritical State
A. Ramesh, R. Balasubramanian
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1491-1505
Technical Paper | doi.org/10.1080/00295639.2022.2147384
Investigation of the Influence of TeO2 on the Elastic and Radiation Shielding Capabilities of Phospho-Tellurite Glasses Doped With Sm2O3
Sangeeta B. Kolavekar, G. B. Hiremath, N. M. Badiger, N. H. Ayachit
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1506-1519
Technical Paper | doi.org/10.1080/00295639.2022.2149232
Impact of the Melt-Refining Process on the Performance of Sodium-Cooled Rotational Fuel-Shuffling Breed-and-Burn Reactors
Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama, Toru Obara
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1520-1533
Technical Paper | doi.org/10.1080/00295639.2022.2153639
Radiation Dose Assessment of Tritium Released from the Thorium Molten Salt Reactor
Wenyu Cheng, Jie Liang, Mingjun Zhang, Fei Wei, Jinglin Li, Xiaochong Xue, Youshi Zeng, Ke Deng, Qin Zhang, Wei Liu
Nuclear Science and Engineering | Volume 197 | Number 7 | July 2023 | Pages 1534-1544
Technical Paper | doi.org/10.1080/00295639.2022.2158020
On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Higher-Order Transport Calculations
Zoltán István Böröczki, Boglárka Babcsány, János Endre Maróti, Máté Szieberth
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1545-1563
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2167469
Geometry Extension and Assemblywise Domain Decomposition of nTRACER for Direct Whole-Core Calculation of VVERs
Seongchan Kim, Han Gyu Joo
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1564-1583
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2144083
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation
Kenneth Assogba, Lahbib Bourhrara, Igor Zmijarevic, Grégoire Allaire, Antonio Galia
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1584-1599
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2154546
Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with Metamodel-Driven Modeling
Peter J. Kowal, Camden E. Blake, Kurt A. Dominesey, Robert A. Lefebvre, Forrest B. Brown, Wei Ji
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1600-1620
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2153617
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method
Satoshi Takeda, Takanori Kitada
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1621-1633
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2123679
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis
Jorge Gonzalez-Amoros, Marianna Papadionysiou, Seongchan Kim, Han Gyu Joo
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1634-1655
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2140577
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries
Emily Shemon, Yinbin Miao, Shikhar Kumar, Kun Mo, Yeon Sang Jung, Aaron Oaks, Scott Richards, Guillaume Giudicelli, Logan Harbour, Roy Stogner
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1656-1680
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2149231
An Inline Burnup Algorithm
P. Cosgrove, E. Shwageraus, J. Leppänen
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1681-1699
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2106732
An Efficient High-to-Low Iterative Method for Light Water Reactor Analysis Based on NEAMS Tools
Kan Ni, Jason Hou
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1700-1716
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2158706
Development of a 3D APOLLO3® Neutron Deterministic Calculation Scheme for the CABRI Experimental Reactor
Tommy Coissieux, Julien Politello, Claire Vaglio-Gaudard, Karim Ammar
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1717-1732
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2167471
Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power Reactor
Guy Shtotland, Assaf Kolin, Benoit Geslot, Patrick Blaise, Nir Kastin
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1733-1742
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2174761
Multiphysics Analysis System for Heat Pipe–Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP
Jaeuk Im, Myung Jin Jeong, Namjae Choi, Kyung Min Kim, Hyoung Kyu Cho, Han Gyu Joo
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1743-1757
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2143209
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor
Hangbok Choi, Darrin Leer, Matthew Virgen, Oscar Gutierrez, John Bolin
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1758-1768
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2158707
Variable Dynamic Mode Decomposition for Estimating Time Eigenvalues in Nuclear Systems
Ethan Smith, Ilham Variansyah, Ryan McClarren
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1769-1778
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2142025
Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron Groups in Heavy Water Reactors
Yanuar Ady Setiawan, Hemantika Sengar, Douglas A. Fynan, Arief Rahman Hakim
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1779-1799
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2103341
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality
J. L. Wormald, J. C. Holmes, M. L. Zerkle
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1800-1813
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2138063
Feynman-α Analysis Using BGO Gamma-Ray Detector in a University Training and Research Reactor
Masaki Goto, Tadafumi Sano, Kunihiro Nakajima, Takashi Kanda, Atsushi Sakon, Kengo Hashimoto
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1814-1822
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2143707
High-Performance and High-Fidelity GPU-Based Monte Carlo Solutions to the BEAVRS Benchmark
Kyung Min Kim, Jaeuk Im, Namjae Choi, Han Gyu Lee, Han Gyu Joo
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1823-1844
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2148812
EBR-II MOX Fuel Characterization Enabling ARES Phase I Testing
John D. Bess, Andrew S. Chipman, Chad L. Pope, Colby B. Jensen, Takayuki Ozawa, Shun Hirooka, Masato Kato
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1845-1872
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2156240
Phonon Sampling Method for Inelastic Thermal Neutron Scattering Events
Amelia Trainer, Benoit Forget
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1873-1886
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2162302
FLASSH 1.0: Thermal Scattering Law Evaluation and Cross-Section Generation for Reactor Physics Applications
N. Colby Fleming, Cole A. Manring, Briana K. Laramee, Jonathan P. W. Crozier, Eunji Lee, Ayman I. Hawari
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1887-1901
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2194195
Core Reload Design Using Genetic Optimization for Cost Savings in a Two-Reactor Power Plant With Used Fuel Sharing
Benjamin Lilley, Todd S. Palmer
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1902-1910
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2171273
Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design
Joshua Ruegsegger, Connor Moreno, Matthew Nyberg, Tim Bohm, Paul P. H. Wilson, Ben Lindley
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1911-1927
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2154118
Multi-Output Gaussian Processes for Inverse Uncertainty Quantification in Neutron Noise Analysis
Paul Lartaud, Philippe Humbert, and Josselin Garnier
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1928-1951
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2143705
Deep Subcriticality Determination Using the Source Jerk Integral Method in the SALMON Program
A. Kochetkov, A. Krása, N. Messaoudi, G. Vittiglio, J. Wagemans, A. Bailly, A. Billebaud, S. Chabod, F.-R. Lecolley, J.-L. Lecouey, G. Lehaut, N. Marie
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1952-1960
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2146429
Study of Reactor Core Loading Monitoring at the GUINEVERE Facility
A. Bailly, J.-L. Lecouey, A. Billebaud, S. Chabod, A. Kochetkov, A. Krása, F.-R. Lecolley, G. Lehaut, N. Marie, N. Messaoudi, G. Vittiglio, J. Wagemans
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1961-1971
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2148813
Horizontal Split-Table Conceptual Design to Support Advanced Reactor Validation Needs
Mathieu N. Dupont, Daniel J. Siefman, Justin B. Clarity, Catherine M. Percher
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1972-1990
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2151785
State of the Art on Doppler Broadening: Modern Developments on the Fuel Temperature Coefficient
David Friant, David Bernard, Patrick Blaise
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 1991-2006
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2158679
Benchmark of Neutron Thermalization in Graphite Using a Pulsed Slowing-Down-Time Experiment
Eunji Lee, N. Colby Fleming, Ayman I. Hawari
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2007-2016
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2162789
Development of Experimental Core Configurations to Clarify keff Variations by Nonuniform Core Configurations
Satoshi Gunji, Shouhei Araki, Kenya Suyama
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2017-2029
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2164151
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering
Imre Pázsit, Victor Dykin, Flynn Darby
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2030-2046
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2178249
A Generalized Eigenvalue Formulation for Core-Design Applications
Nicolo’ Abrate, Sandra Dulla, Piero Ravetto, Paolo Saracco
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2047-2071
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2134685
Transition Core Modeling for Extended-Enrichment Accident-Tolerant Fuels in Light Water Reactors Using PARCS/Polaris
Muhammad Rizki Oktavian, Ugur Mertyurek, Yunlin Xu
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2072-2085
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2162790
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design
Alexis Maldonado, Christopher Perfetti
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2086-2098
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2162782
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors
Rohan Biwalkar, Kenneth Redus, Adam Stein, Sola Talabi
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2099-2116
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2204174
Using a Random Forest Model to Choose Optimized Group Structures
Thomas G. Saller, Vishnu Nair, Andrew Till, Nathan Gibson
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2117-2135
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2133940
Improving the Predictivity of a Steam Generator Clogging Numerical Model by Global Sensitivity Analysis and Bayesian Calibration Techniques
L. Lefebvre, M. Segond, R. Spaggiari, L. Le Gratiet, E. Deri, B. Iooss, G. Damblin
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2136-2149
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2206769
Neutronic Evaluation and Optimization of the Centrifugal Nuclear Thermal Rocket Concept
William J. Walters
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2150-2160
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2161805
Feasibility of Using Poisons to Suppress the Positive Temperature Reactivity Coefficient in Hydride-Moderated Reactors
Vedant K. Mehta, Zachary A. Miller, Dasari V. Rao
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2161-2175
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2164150
Design of a Fast Molten Salt Reactor for Space Nuclear Electric Propulsion
F. Quinteros, P. Rubiolo, V. Ghetta, J. Giraud, N. Capellan
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2176-2191
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2023.2167470
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design
Alex Aimetta, Nicolò Abrate, Sandra Dulla, Antonio Froio
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2192-2216
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2153638
The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor Models Using NEAMS Tools
Guillaume L. Giudicelli, Abdalla Abou-Jaoude, April J. Novak, Ahmed Abdelhameed, Paolo Balestra, Lise Charlot, Jun Fang, Bo Feng, Thomas Folk, Ramiro Freile, Thomas Freyman, Derek Gaston, Logan Harbour, Thanh Hua, Wen Jiang, Nicolas Martin, Yinbin Miao, Jason Miller, Isaac Naupa, Dan O’Grady, David Reger, Emily Shemon, Nicolas Stauff, Mauricio Tano, Stefano Terlizzi, Samuel Walker, Cody Permann
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2217-2233
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2142440
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations
Olin W. Calvin, Micah D. Gale, Sebastian Schunert
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2234-2250
Technical papers from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2161802
Reactor Physics Experiment on a Graphite-Moderated Core to Construct Integral Experiment Database for HTGR
Shoichiro Okita, Yuji Fukaya, Atsushi Sakon, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki
Nuclear Science and Engineering | Volume 197 | Number 8 | August 2023 | Pages 2251-2257
Technical Note from: PHYSOR 2022 | doi.org/10.1080/00295639.2022.2087836
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine
Mario Marengo, Gianfranco Cicoria, Angelo Infantino, Sara Vichi, Federico Zagni, Domiziano Mostacci
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2259-2269
Review Article | doi.org/10.1080/00295639.2022.2146433
Benchmark Solutions for Radiative Transfer with a Moving Mesh and Exact Uncollided Source Treatments
William Bennett, Ryan G. McClarren
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2270-2300
Research Article | doi.org/10.1080/00295639.2023.2199783
Acceleration Waves in Cylindrical Shrinking Gas Bubbles
Francesca Brini, Leonardo Seccia
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2301-2316
Research Article | doi.org/10.1080/00295639.2023.2166754
A New Approach for NaI(Tl) Detector Efficiency Calibration Using 41Ar Radionuclide for Air Exhaust Systems
Mahsa Farasat, Federico Zagni, Lorenzo Pompignoli, G. A. Pablo Cirrone, Ulrich W. Scherer, Lidia Strigari, Domiziano Mostacci
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2317-2326
Research Article | doi.org/10.1080/00295639.2022.2164148
Response Matrix/Discrete Ordinates Solution of the 1D Fokker-Planck Equation
B. D. Ganapol, Ó. López Pouso
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2327-2342
Research Article | doi.org/10.1080/00295639.2023.2194228
Frequency-Dependent Discrete Implicit Monte Carlo Scheme for the Radiative Transfer Equation
Elad Steinberg, Shay I. Heizler
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2343-2355
Research Article | doi.org/10.1080/00295639.2023.2190728
Neutron Multiplicity Counting Distribution Reconstruction from Moments Using Meixner Polynomial Expansion and N-Forked Branching Approximations
Philippe Humbert
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2356-2372
Research Article | doi.org/10.1080/00295639.2022.2162304
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations
Laura Laghi, Enrico Schiassi, Mario De Florio, Roberto Furfaro, Domiziano Mostacci
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2373-2403
Research Article | doi.org/10.1080/00295639.2022.2160604
Asymptotic Expansion of the Angular Flux Applied to Discrete-Ordinates Source Iterations in Lattice Depletion Calculations
E. Masiello, F. Filiciotto, S. Lapuerta-Cochet, R. Lenain
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2404-2424
Research Article | doi.org/10.1080/00295639.2023.2175583
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect
F. Filiciotto, E. Masiello, S. Cochet-Lapuerta, R. Lenain
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2425-2445
Research Article | doi.org/10.1080/00295639.2022.2151783
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas
Vincenzo Molinari, Domiziano Mostacci, Francesco Teodori
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2446-2449
Research Article | doi.org/10.1080/00295639.2023.2194199
Numerical Study of the Influence of Collisions on Oscillations of the Electric Field for the Vlasov-Poisson-Landau Kinetic Equation
Irina Potapenko, Stanislav Karpov
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2450-2458
Research Article | doi.org/10.1080/00295639.2023.2189511
Towards a Systematic Requirement-Based Approach to Build a Neutronics Study Platform
Alberto Previti, Alberto Brighenti, Damien Raynaud, Barbara Vezzoni
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2459-2483
Research Article | doi.org/10.1080/00295639.2023.2189535
Physics-Informed Neural Network with Fourier Features for Radiation Transport in Heterogeneous Media
Quincy A. Huhn, Mauricio E. Tano, Jean C. Ragusa
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2484-2497
Research Article | doi.org/10.1080/00295639.2023.2184194
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods
Dingkang Zhang, Farzad Rahnema
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2498-2508
Research Article | doi.org/10.1080/00295639.2023.2196936
The Maximum Entropy Principle: General Extended Hydrodynamic Approach for Dynamic High-Field Transport in Monolayer Graphene
M. Trovato, P. Falsaperla, L. Reggiani
Nuclear Science and Engineering | Volume 197 | Number 9 | September 2023 | Pages 2509-2525
Research Article | doi.org/10.1080/00295639.2023.2199832
A Perspective on Data-Driven Coarse Grid Modeling for System-Level Thermal Hydraulics
Arsen S. Iskhakov, Cheng-Kai Tai, Igor A. Bolotnov, Nam T. Dinh
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2527-2542
Research Article | doi.org/10.1080/00295639.2022.2107864
myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment
H. J. Uitslag-Doolaard, K. Zwijsen, F. Roelofs, M. M. Stempniewicz
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2543-2560
Research Article | doi.org/10.1080/00295639.2022.2148809
Coupled Monte Carlo Transport and Conjugate Heat Transfer for Wire-Wrapped Bundles Within the MOOSE Framework
A. J. Novak, P. Shriwise, P. K. Romano, R. Rahaman, E. Merzari, D. Gaston
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2561-2584
Research Article | doi.org/10.1080/00295639.2022.2158715
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow
E. M. A. Frederix, S. Tajfirooz, J. A. Hopman, J. Fang, E. Merzari, E. M. J. Komen
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2585-2601
Research Article | doi.org/10.1080/00295639.2022.2141517
Euler-Euler Model of Bubbly Flow Using Particle-Center-Averaging Method
Hongmei Lyu, Fabian Schlegel, Roland Rzehak, Dirk Lucas
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2602-2619
Research Article | doi.org/10.1080/00295639.2022.2131344
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model
Fabian Schlegel, Richard Meller, Benjamin Krull, Ronald Lehnigk, Matej Tekavčič
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2620-2633
Research Article | doi.org/10.1080/00295639.2022.2120316
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor
Tri Nguyen, Elia Merzari
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2634-2659
Research Article | doi.org/10.1080/00295639.2023.2186200
Code Benchmark of the HTTF Pressurized Conduction Cooldown Test Using SAM
Thanh Hua, Ling Zou, Rui Hu
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2660-2672
Research Article | doi.org/10.1080/00295639.2023.2186163
Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments
E. Schmidt, N. Reinke, M. Freitag, M. Sonnenkalb
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2673-2685
Research Article | doi.org/10.1080/00295639.2022.2146994
Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood
Grant R. Garrett, Brian R. Lowery, Molly K. Hanson, Douglas J. Miller, Turki Almudhhi, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2686-2710
Research Article | doi.org/10.1080/00295639.2022.2157189
Experimental Analysis of Fast-Transient Flow Boiling in Various Flow Conditions Using Inverse Heat Conduction Calculation Method
Yong-Seok Choi, Dong-Hoon Kam, Byong-Guk Jeon, Jong-Kuk Park, Sang-Ki Moon
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2711-2722
Research Article | doi.org/10.1080/00295639.2022.2132100
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms
Fred Gelbard, Bradley A. Beeny, Larry L. Humphries, Kenneth C. Wagner, Lucas I. Albright, Max Poschmann, Markus H. A. Piro
Nuclear Science and Engineering | Volume 197 | Number 10 | October 2023 | Pages 2723-2741
Research Article | doi.org/10.1080/00295639.2022.2161277
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants
John Stamatakos, Biswajit Dasgupta, Osvaldo Pensado, Nilesh Chokshi, Robert Budnitz, M. K. Ravindra
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2743-2750
PSA 2021 Paper | doi.org/10.1080/00295639.2022.2158701
A Method for Backward Failure Propagation in Conceptual System Design
Ali Mansoor, Xiaoxu Diao, Carol Smidts
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2751-2777
PSA 2021 Paper | doi.org/10.1080/00295639.2023.2196937
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model
Claudia Picoco, Valentin Rychkov
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2778-2786
PSA 2021 Paper | doi.org/10.1080/00295639.2023.2196227
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms
Yochan Kim, Jinkyun Park, Mary Presley
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2787-2799
PSA 2021 Paper | doi.org/10.1080/00295639.2022.2118481
Discrete-Time Bayesian Networks Applied to Flexible Coping Strategies of Nuclear Power Plant Systems
Elvan Sahin, Victor C. Leite, Kyung M. Kim, Nick Burns, Juliana Pacheco Duarte
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2800-2817
PSA 2021 Paper | doi.org/10.1080/00295639.2022.2151300
Sensitivity Analysis of Effectiveness of FLEX Strategies Using a CDF-Based Importance Measure Under Accident Conditions
Asad Ullah Amin Shah, Junyung Kim, Robby Christian, Hyun Gook Kang
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2818-2829
PSA 2021 Paper | doi.org/10.1080/00295639.2023.2194460
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release
Anjun Jiao, David Ricks, Thomas Remick, Brian J. Hansen
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2830-2839
Regular Research Article | doi.org/10.1080/00295639.2023.2171274
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies
Sean M. McDeavitt, David Wootan, Mark Kimber, Karen Vierow Kirkland, Luis H. Ortega, Delia Perez-Nunez, Pavel Tsvetkov, Jason Hearne, Abdullah Weiss, Saleem Drera, Nicolas E. Woolstenhulme
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2840-2852
Regular Research Article | doi.org/10.1080/00295639.2023.2166765
Goal-Oriented Mesh Adaptivity of Three-Dimensional Neutron Transport Calculation Using Weighted Difference Scheme and Dual-Weighted Residual Error Indicators
Cong Liu, Junxia Wei, Bin Zhang, Jinhong Li, Zhiqiang Sheng, Shuang Tan
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2853-2883
Regular Research Article | doi.org/10.1080/00295639.2023.2169537
Inversion Point of the Isothermal Reactivity Coefficient with Increasing System Temperature in a Heterogeneous Core Lattice of a Light Water Reactor
Mathieu N. Dupont, Matthew D. Eklund, Peter F. Caracappa, Wei Ji
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2884-2901
Regular Research Article | doi.org/10.1080/00295639.2023.2172307
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly
Cheol Ho Pyeon, Ryota Katano, Akito Oizumi, Masahiro Fukushima
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2902-2919
Regular Research Article | doi.org/10.1080/00295639.2023.2172311
Improved Methods for Calculating the Neutron Diffusion Coefficient of General Pebble Bed
Yutong Wen, Ding She, Lei Shi
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2920-2934
Regular Research Article | doi.org/10.1080/00295639.2023.2172312
Computationally Optimized Irradiation Chamber Design for Production of 135Xe in the Washington State University TRIGA Reactor
Tanner W. Hall, Meng-Jen (Vince) Wang, Glenn E. Sjoden, Matthew Watrous, Corey Hines
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2935-2949
Regular Research Article | doi.org/10.1080/00295639.2023.2178227
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film
Hajime Furuichi, Kenichi Katono, Yuki Mizushima, Toshiyuki Sanada
Nuclear Science and Engineering | Volume 197 | Number 11 | November 2023 | Pages 2950-2960
Regular Research Article | doi.org/10.1080/00295639.2023.2180986
Investigation of Normal and Abnormal States of the Molten Salt Experimental Loop Using Computational Fluid Dynamics
Michal Cihlář, Pavel Zácha, Jan Uhlíř, Martin Mareček, Václav Dostál, Jan Prehradný
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 2961-2976
YMSR Paper | doi.org/10.1080/00295639.2023.2189549
Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design
Nicolo’ Abrate, Alex Aimetta, Sandra Dulla, Nicola Pedroni
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 2977-2999
YMSR Paper | doi.org/10.1080/00295639.2023.2190861
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD
Nathan Greiner, François Madiot, Yannick Gorsse, Cyril Patricot, Guillaume Campioni
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3000-3021
YMSR Paper | doi.org/10.1080/00295639.2023.2197043
Modeling Flow Blockage Accident in Graphite-Moderated Molten Salt Reactors
Paolo Bianchini, Manuele Aufiero, Francesco Di Lecce
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3022-3034
YMSR Paper | doi.org/10.1080/00295639.2023.2219818
Thermodynamic Assessment of the NaCl-CrCl2, NaCl-CrCl3, and FeCl2-CrCl2 Pseudo-Binary Systems for Describing the Corrosion Chemistry Between Molten Salt Fuel and Steel
V. Tiwari, T. F. Abbink, J. A. Ocádiz Flores, J. L. Flèche, C. Gueneau, S. Chatain, A. L. Smith, J. Martinet, C. Venard
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3035-3057
YMSR Paper | doi.org/10.1080/00295639.2023.2223745
Numerical Modeling and Simulation of Melting Phenomena for Freeze Valve Analysis in Molten Salt Reactors
Davide Tartaglia, Antonio Cammi, Carolina Introini, Stefano Lorenzi
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3058-3081
YMSR Paper | doi.org/10.1080/00295639.2023.2229576
Pumping Options for Versatile Test Reactor Molten Lead In-Pile Test Cartridge
Mohamed S. El-Genk, Timothy M. Schriener, Ragai Altamimi, Andrew Hahn
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3082-3109
Regular Research Article | doi.org/10.1080/00295639.2023.2190723
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 241Pu
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3110-3124
Regular Research Article | doi.org/10.1080/00295639.2023.2190725
Neutron Measurements and Monte Carlo Simulations of Spent Nuclear Fuel in Dry Cask Storage Using a New Remote Monitoring System Prototype
Jeremy W. King, Craig M. Marianno, Sunil S. Chirayath
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3125-3137
Regular Research Article | doi.org/10.1080/00295639.2023.2191579
Solving the Neutron Transport Equation for Microreactor Modeling Using Unstructured Meshes and Exascale Computing Architectures
William C. Dawn, Scott Palmtag
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3138-3159
Regular Research Article | doi.org/10.1080/00295639.2023.2189510
Effect of Oxygen Ion Irradiation on Nb-1Zr-0.1C Alloy Characterized Using X-Ray Diffraction Line Profile Analysis
Argha Dutta, Apu Sarkar, Sandip Bysakh, Uttiyoarnab Saha, N. Gayathri, Santu Dey, P. Mukherjee
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3160-3174
Regular Research Article | doi.org/10.1080/00295639.2023.2191580
Development of Multiphysics Framework to Analyze Dynamic Gap Heat Transfer and Cross-Flow Effect on Partial Rod Ejection Accident
Awais Zahur, Muhammad Rizwan Ali, Deokjung Lee
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3175-3192
Technical Note | doi.org/10.1080/00295639.2023.2189888
