ANS / Publications / Journals / Nuclear Science and Engineering

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2022.2103338

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2022.2129224

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2022.2154114

Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled to 3D FEM Thermal Diffusion Models

Ross Pivovar, Rebecca Owston

Nuclear Science and Engineering / Volume 197 / Number 4 / April 2023 / Pages 686-702

Computer Code Abstract / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2022.2143208

Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced Fission of ²³³U

H. Naik, S. P. Dange, R. J. Singh, W. Jang

Nuclear Science and Engineering / Volume 197 / Number 6 / June 2023 / Pages 1133-1158

Technical Paper / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2022.2138064

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2022.2162789

Development of Experimental Core Configurations to Clarify k_eff 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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2190723

Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹Pu

H. Naik, R. J. Singh, S. P. Dange, W. Jang

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3110-3124

Regular Research Article / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2189888