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2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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Vogtle-3 achieves full power output
The Vogtle expansion project’s Unit 3 reactor has attained 100 percent energy output—the first time it has reached its maximum expected output of approximately 1,100 MWe, Georgia Power announced yesterday.
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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
