ANS / Publications / Journals / Nuclear Science and Engineering

Adjoint Klein-Nishina Sampling Methods: Efficiency, Speed, and Applications

Alex P. Robinson, Douglass Henderson, Luke Kersting, Eli Moll

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 1-15

Technical Paper / dx.doi.org/10.1080/00295639.2021.1935103

Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²³⁷Np

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

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 16-39

Technical Paper / dx.doi.org/10.1080/00295639.2021.1951078

Theoretical Calculations and Evaluations of Neutron-Induced Reactions on ¹²¹Sb, ¹²³Sb, and Natural Sb

Hairui Guo, Wendi Chen, Yinlu Han, Xiaojun Sun, Tao Ye, Weili Sun

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 40-52

Technical Paper / dx.doi.org/10.1080/00295639.2021.1940067

The Finite-Element with Discontiguous-Support Method

Andrew T. Till, Marvin L. Adams, Jim E. Morel

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 53-74

Technical Paper / dx.doi.org/10.1080/00295639.2021.1932224

Experimental and Numerical Investigation into Temperature Distribution of a Simulated PHWR Coolant Channel Under Heatup Condition

Ketan Ajay, Ravi Kumar, Akhilesh Gupta

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 75-97

Technical Paper / dx.doi.org/10.1080/00295639.2021.1945393

Parametric Study of Minimum Critical Volume for High-Assay Low-Enriched Uranium (20%) in Spherical Geometry Against Particle Size

Joseph A. Christensen, R. A. Borrelli

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 98-108

Technical Paper / dx.doi.org/10.1080/00295639.2021.1940066

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 196 / Number 1 / January 2022 / Pages 109-120

Technical Paper / dx.doi.org/10.1080/00295639.2021.1951063

Metallic Fuel Performance Benchmarks for Versatile Test Reactor Applications

Jacob A. Hirschhorn, Jeffrey J. Powers, Ian Greenquist, Ryan T. Sweet, Jianwei Hu, Douglas L. Porter, Douglas C. Crawford

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S123-S147

Technical Paper / dx.doi.org/10.1080/00295639.2022.2043539

Development of Sodium Fire Analysis Code Capabilities for Versatile Test Reactor

Anton Moisseytsev, Matthew Bucknor, James J. Sienicki

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S323-S336

Technical Paper / dx.doi.org/10.1080/00295639.2021.2018925

Preliminary Analysis of Unprotected Transients in the VTR

Tyler Sumner, Tingzhou Fei

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S309-S322

Technical Paper / dx.doi.org/10.1080/00295639.2021.2009982

Modeling of Safety Basis Events in the VTR

Tyler Sumner, Anton Moisseytsev, Daniel O’Grady, Lander Ibarra, Christopher Keckler, Justin Thomas, Thomas Fanning, Carlo Parisi, Nolan Anderson, Frederick Gleicher, SuJong Yoon

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S289-S308

Technical Paper / dx.doi.org/10.1080/00295639.2022.2053487

Development of the Versatile Test Reactor Probabilistic Risk Assessment

David Grabaskas, Jason Andrus, Dennis Henneke, Jonathan Li, Matthew Bucknor, Matthew Warner

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S278-S288

Technical Paper / dx.doi.org/10.1080/00295639.2021.2014741

Digital Engineering for Integrated Modeling and Simulation for Building-Piping Systems Through Interoperability Solutions

Nicholas Crowder, Joomyung Lee, Abhinav Gupta, Kevin Han, Saran Bodda, Christopher Ritter

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S260-S277

Technical Paper / dx.doi.org/10.1080/00295639.2022.2055705

Design and Control of a Fueled Molten Salt Cartridge Experiment for the Versatile Test Reactor

Joel McDuffee, Rich Christensen, Daniel Eichel, Mike Simpson, Supathorn Phongikaroon, Xiaodong Sun, John Baird, Adam Burak, Shay Chapel, Joonhyung Choi, Jacob Gorton, D. Ethan Hamilton, Dimitris Killinger, Sam Miller, Jason Palmer, Christian Petrie, Daniel Sweeney, Adrian Schrell, James Vollmer

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S234-S259

Technical Paper / dx.doi.org/10.1080/00295639.2021.2017663

Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II

Piyush Sabharwall, Kevan Weaver, N. K. Anand, Chris Ellis, Xiaodong Sun, Hangbok Choi, Di Chen, Rich Christensen, Brian M. Fronk, Joshua Gess, Yassin Hassan, Igor Jovanovic, Annalisa Manera, Victor Petrov, Rodolfo Vaghetto, Silvino Balderrama-Prieto, Adam J. Burak, Milos Burger, Alberto Cardenas-Melgar, Daniel Orea, Reynaldo Chavez, Byunghee Choi, Londrea Garrett, Genevieve L. Gaudin, Noah Sutton, Ken Willams, Josh Young

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S215-S233

Technical Paper / dx.doi.org/10.1080/00295639.2022.2070384

Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor—Part I

Piyush Sabharwall, Kevan Weaver, N. K. Anand, Chris Ellis, Xiaodong Sun, Di Chen, Hangbok Choi, Rich Christensen, Brian M. Fronk, Joshua Gess, Yassin Hassan, Igor Jovanovic, Annalisa Manera, Victor Petrov, Rodolfo Vaghetto, Silvino Balderrama-Prieto, Adam J. Burak, Milos Burger, Alberto Cardenas-Melgar, Londrea Garrett, Genevieve L. Gaudin, Daniel Orea, Reynaldo Chavez, Byunghee Choi, Noah Sutton, Ken Williams, Josh Young

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S183-S214

Technical Paper / dx.doi.org/10.1080/00295639.2022.2070383

Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR

Seung Jun Kim, Keith Woloshun, Joshua Richard, Jack Galloway, Cetin Unal, Jeffrey Arndt, Michael Ickes, Paolo Ferroni, Richard Wright, Osman Anderoglu, Cemal Cakez, Khaled Talaat, Shuprio Ghosh, Brandon Bohannon

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S165-S182

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011572

Development of a Sodium Fast Reactor Cartridge Loop Testing Capability for the Versatile Test Reactor

Mitchell T. Farmer, Matthew Weathered, Darius Lisowski, Nathan Bremer, Dennis Kilsdonk, Tim Stack, Caleb Tomlin, Chris Plucker, Ed Moreno, Ran Kong, Zhengting Quan, Adam Dix, Seungjin Kim, Mamoru Ishii, Mark Anderson, Andrew Napora

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S148-S164

Technical Paper / dx.doi.org/10.1080/00295639.2022.2052552

The Versatile Test Reactor Project: Mission, Requirements, and Description

Jordi Roglans-Ribas, Kemal Pasamehmetoglu, Thomas J. O’Connor

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S1-S10

Technical Paper / dx.doi.org/10.1080/00295639.2022.2035183

Fuel Performance Design Basis for the Versatile Test Reactor

D. L. Porter, D. C. Crawford

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S110-S122

Technical Paper / dx.doi.org/10.1080/00295639.2021.2009983

Radiation Protection and Shielding Analysis of the Versatile Test Reactor

Tingzhou Fei, Zhaopeng Zhong, Samuel E. Bays, Florent Heidet

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S98-S109

Technical Paper / dx.doi.org/10.1080/00295639.2021.1991760

Design of Experiments to Support VTR Core Design

Darius Lisowski, Alex Grannan, Matthew Jasica, SuJong Yoon, Florent Heidet

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S83-S97

Technical Paper / dx.doi.org/10.1080/00295639.2022.2043540

Validation Efforts for the Versatile Test Reactor

Micheal A. Smith, Richard M. Lell, Gerardo Aliberti, Zhaopeng Zhong, Florent Heidet

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S71-S82

Technical Paper / dx.doi.org/10.1080/00295639.2022.2058845

Uncertainty Quantification Approach for the Versatile Test Reactor Core Design

Adam G. Nelson, Nicolas Martin, Alisha Kasam-Griffith, Zhiwen Xu, Florent Heidet

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S63-S70

Technical Paper / dx.doi.org/10.1080/00295639.2022.2035181

Supporting Design Analysis of the VTR Using MCNP and TRACE

Jack Galloway, Joshua Richard, Cetin Unal

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S50-S62

Technical Paper / dx.doi.org/10.1080/00295639.2022.2053488

VTR Core Design Analyses Supporting Flexible Operations

Alisha Kasam-Griffith, Milos Atz, Tingzhou Fei, Zhaopeng Zhong, Michael Jarrett, Florent Heidet

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S38-S49

Technical Paper / dx.doi.org/10.1080/00295639.2022.2031712

Versatile Test Reactor Conceptual Core Design

F. Heidet, J. Roglans-Ribas

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S23-S37

Technical Paper / dx.doi.org/10.1080/00295639.2022.2091907

Current State of the Design Engineering of the Versatile Test Reactor Plant

Steven Unikewicz, Eric Loewen, George Malone

Nuclear Science and Engineering / Volume 196 / Number 1S / October 2022 / Pages S11-S22

Technical Paper / dx.doi.org/10.1080/00295639.2022.2027738

Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV

E. Blain, Y. Danon, D. P. Barry, B. E. Epping, A. Youmans, M. J. Rapp, A. M. Daskalakis, R. C. Block

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 121-132

Technical Paper / dx.doi.org/10.1080/00295639.2021.1961542

Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data

Fuga Nishioka, Tomohiro Endo, Akio Yamamoto, Masao Yamanaka, Cheol Ho Pyeon

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 133-143

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968225

Transport Corrections and Sensitivities in the Discrete-Ordinates Method

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 144-160

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968224

A Stable Method for Solving the Simplified Time-Dependent Neutron Transport Equation with Background Motion

Longfei Xu, Huayun Shen, Junxia Wei, Liujun Pan

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 161-182

Technical Paper / dx.doi.org/10.1080/00295639.2021.1941565

Optimal Batch Size Growth for Wielandt Method and Superhistory Method

Qingquan Pan, Tengfei Zhang, Xiaojing Liu, Yun Cai, Lianjie Wang, Kan Wang

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 183-192

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968223

Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment

Alexander Duenas, Daniel Wachs, Guillaume Mignot, Jose N. Reyes, Qiao Wu, Wade Marcum

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 193-208

Technical Paper / dx.doi.org/10.1080/00295639.2021.1955591

Study on LOFA and LOHS Accidents with Passive Safety System for Integrated Marine Reactor

Dong Li, Rao Hao

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 209-220

Technical Paper / dx.doi.org/10.1080/00295639.2021.1968760

Stress Distribution and Safety Evaluation of Pipeline in Ice Plug of Nuclear Power

Linjun Xie, Changxun Wang, Wei Zhang, Xin Shen, Minglei Hu, Chunhua Bian, Yilun Xu

Nuclear Science and Engineering / Volume 196 / Number 2 / February 2022 / Pages 221-233

Technical Note / dx.doi.org/10.1080/00295639.2021.1964325

Transport Calculation of the Multiplicity Moments for Cylinders

Imre Pázsit, Victor Dykin

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 235-249

Technical Paper / dx.doi.org/10.1080/00295639.2021.1973178

Analytical Discrete Ordinates Solution for a 1D Model of Particle Transport in Ducts that Includes Wall Migration

R. D. M. Garcia

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 250-275

Technical Paper / dx.doi.org/10.1080/00295639.2021.1975480

Modeling Interface Debonding in Coated Fuel Particles with BISON

Daniel Schappel, Giovanni Pastore, Kurt A. Terrani

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 276-284

Technical Paper / dx.doi.org/10.1080/00295639.2021.1955590

Experimental Investigation of the Friction Factor of Wire-Wrapped Bundles at Low Velocities Under Natural Circulation Flow Conditions

Hongyi Yang, Hongrui Li, Xiuli Xue, Zhiwei Zhou

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 285-300

Technical Paper / dx.doi.org/10.1080/00295639.2021.1973177

The ICSCREAM Methodology: Identification of Penalizing Configurations in Computer Experiments Using Screening and Metamodel—Applications in Thermal Hydraulics

A. Marrel, B. Iooss, V. Chabridon

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 301-321

Technical Paper / dx.doi.org/10.1080/00295639.2021.1980362

Neutron Balance Features in Breed-and-Burn Fast Reactors

Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 322-341

Technical Paper / dx.doi.org/10.1080/00295639.2021.1980361

Analyzing APR1400 System Response Under Load Follow Operation Using a Multiphysics Approach

Abd El Rahman Mahmoud, Aya Diab

Nuclear Science and Engineering / Volume 196 / Number 3 / March 2022 / Pages 342-361

Technical Note / dx.doi.org/10.1080/00295639.2021.1975479

Solution Irregularity Remediation for Spatial Discretization Error Estimation for S_N Transport Solutions

Nathan H. Hart, Yousry Y. Azmy

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 363-378

Technical Paper / dx.doi.org/10.1080/00295639.2021.1982548

Impact of Angular and Spatial Source Distribution Approximations on Convergence Performance of Nonlinear Acceleration Methods for MOC in Slab Geometry

Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 379-394

Technical Paper / dx.doi.org/10.1080/00295639.2021.1982549

Modification of a Dynamic Monte Carlo Technique to Simplify and Accelerate Transient Analysis with Feedback

Meysam Ghaderi Mazaher, Ali Akbar Salehi, Naser Vosoughi

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 395-408

Technical Paper / dx.doi.org/10.1080/00295639.2021.1989932

Direct Comparison of High-Order/Low-Order Transient Methods on the 2D-LRA Benchmark Problem

Miriam A. Kreher, Kord Smith, Benoit Forget

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 409-432

Technical Paper / dx.doi.org/10.1080/00295639.2021.1980363

Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced Fission of ²³²U

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

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 433-454

Technical Paper / dx.doi.org/10.1080/00295639.2021.1993425

A Versatile Methodology for Reactor Pressure Vessel Aging Assessments

Romain Vuiart, Mariya Brovchenko, Julien Taforeau, Vaibhav Jaiswal, Eric Dumonteil

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 455-477

Technical Paper / dx.doi.org/10.1080/00295639.2021.1991761

A Study of Nuclear Fuel Burnup Wave Development in a Fast Neutron Energy Spectrum Multiplying Medium: Improved Model and Consistent Parametric Approach for Evaluation

Dipanjan Ray, Manish Kumar, Om Pal Singh, Prabhat Munshi

Nuclear Science and Engineering / Volume 196 / Number 4 / April 2022 / Pages 478-496

Technical Note / dx.doi.org/10.1080/00295639.2021.1987134

Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation

Zack Taylor, Benjamin S. Collins, G. Ivan Maldonado

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 497-525

Technical Paper / dx.doi.org/10.1080/00295639.2021.1996197

A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation

Chao Fang, Liangzhi Cao, Hongchun Wu, Kang Li

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 526-543

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011667

Real-Time Monitoring for Detection of Adversarial Subtle Process Variations

Yeni Li, Arvind Sundaram, Hany S. Abdel-Khalik, Paul W. Talbot

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 544-567

Technical Paper / dx.doi.org/10.1080/00295639.2021.1997041

Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5

Fabiano Gibson Daud Thulu, Ayah Elshahat, Mohamed Hassan

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 568-583

Technical Paper / dx.doi.org/10.1080/00295639.2021.2009984

Deposition Behavior of Cesium Molybdate on Type 304 Austenite Stainless Steel in Severe Accident

Thi-Mai-Dung Do, Supamard Sujatanond, Toru Ogawa

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 584-599

Technical Paper / dx.doi.org/10.1080/00295639.2021.2009985

Numerical Evaluation for Spacer Vane Effects on Flow and Heat Transfer of Water at Supercritical Pressure in Annular Channel

Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 600-613

Technical Paper / dx.doi.org/10.1080/00295639.2021.2003650

A Study of Gamma Heating, Neutron Flux, and Gamma Flux Under Several Reactor Core Conditions in the McMaster Nuclear Reactor

Mohammed Alqahtani, Adriaan Buijs, Meshari ALQahtani

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 614-622

Technical Paper / dx.doi.org/10.1080/00295639.2021.2003651

Effect of Cladding Surface Roughness on Thermal-Hydraulic Response of Nuclear Fuel Rod of Advanced Gas-Cooled Reactor

Sadek Hossain Nishat, Md. Hossain Sahadath, Farhana Islam Farha

Nuclear Science and Engineering / Volume 196 / Number 5 / May 2022 / Pages 623-636

Technical Note / dx.doi.org/10.1080/00295639.2021.2003644

Analysis of Corner Balance Nonlinear Diffusion Acceleration and Moment-Based, Spatially Linear Transport Discretizations

Rodolfo M. Ferrer, HyeongKae Park

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 637-650

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011668

Triangular Polynomial Expansion Nodal Method for VVER Core Analysis

Muhammad Rizki Oktavian, Oscar Lastres, Yuxuan Liu, Yunlin Xu

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 651-667

Technical Paper / dx.doi.org/10.1080/00295639.2021.2017664

Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics

Helin Gong, Sibo Cheng, Zhang Chen, Qing Li

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 668-693

Technical Paper / dx.doi.org/10.1080/00295639.2021.2014752

Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴³Am

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

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 694-714

Technical Paper / dx.doi.org/10.1080/00295639.2021.2014753

Bifurcation Analysis of Xenon Oscillations in Large Pressurized Heavy Water Reactors with Spatial Control

Abhishek Chakraborty, Suneet Singh, M. P. S. Fernando

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 715-734

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011670

Validation and Optimization of Activity Estimates of the FiR 1 TRIGA Research Reactor Biological Shield Concrete

Antti Räty, Merja Tanhua-Tyrkkö, Petri Kotiluoto, Tommi Kekki

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 735-750

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011671

Gas-Liquid Two-Phase Flow Regime in a Horizontal Channel Under Transverse Vibration

Bo Sun, Yunlong Zhou

Nuclear Science and Engineering / Volume 196 / Number 6 / June 2022 / Pages 751-768

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011669

Improvements in Computational Efficiency for Resonance Calculation Using Energy Spectrum Expansion Method

Ryoichi Kondo, Tomohiro Endo, Akio Yamamoto, Satoshi Takeda, Hiroki Koike, Kazuya Yamaji, Koji Asano

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 769-791

Technical Paper / dx.doi.org/10.1080/00295639.2021.2025297

Lie Group Analysis of the Integral Equations Related to Neutron Slowing-Down Theory

Patrick O’Rourke, Scott Ramsey, Brian Temple

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 792-810

Technical Paper / dx.doi.org/10.1080/00295639.2021.2018926

A Machine Learning Method for the Forensics Attribution of Separated Plutonium

Patrick J. O’Neal, Sunil S. Chirayath, Qi Cheng

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 811-823

Technical Paper / dx.doi.org/10.1080/00295639.2021.2024037

Post-Neutron Mass Yield Distribution in the Thermal Neutron–Induced Fission of ²³⁹Pu

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

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 824-851

Technical Paper / dx.doi.org/10.1080/00295639.2021.2025298

On the Numerical Method for Photofission-Based Nuclear Material Isotopic Composition Estimation in Thorium-Uranium Systems

Kim Wei Chin, Rei Kimura, Hiroshi Sagara, Kosuke Tanabe

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 852-872

Technical Paper / dx.doi.org/10.1080/00295639.2021.2018927

The Solitary Wave in Advanced Nuclear Energy System

Jin Feng Huang

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 873-885

Technical Paper / dx.doi.org/10.1080/00295639.2021.2025299

Nuclear Reactor Power Level Model Predictive Control: A Consideration of Coolant Outlet Temperature Relaxation Tracking Method

Yuanjie Fang, Minrui Fei, Hong Qian, Ling Wang, Kai Chen

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 886-898

Technical Paper / dx.doi.org/10.1080/00295639.2022.2027737

Thermal-Mechanical Analysis of Beam Window and Beam Tube for ADS Granular Flow Target

Weiping Deng, Yanbin Zhang, Huan Jia, Tao Wan, Weifeng Yang, Chengwen Qiang, Long Li, Fei Wang, Honglin Ge, Fei Ma, Xueying Zhang

Nuclear Science and Engineering / Volume 196 / Number 7 / July 2022 / Pages 899-909

Technical Paper / dx.doi.org/10.1080/00295639.2022.2027177

Deceptive Infusion of Data: A Novel Data Masking Paradigm for High-Valued Systems

Arvind Sundaram, Hany Abdel-Khalik, Ahmad Al Rashdan

Nuclear Science and Engineering / Volume 196 / Number 8 / August 2022 / Pages 911-926

Technical Paper / dx.doi.org/10.1080/00295639.2022.2043542

Investigation on the Use of the Monte Carlo Iterative k-Source Scheme for the Study of Neutron Subcritical Multiplication

Amod Kishore Mallick, Anurag Gupta, Umasankari Kannan

Nuclear Science and Engineering / Volume 196 / Number 8 / August 2022 / Pages 927-942

Technical Paper / dx.doi.org/10.1080/00295639.2022.2043541

Symmetry Groups of the Forward Master Equation for Stochastic Neutron Populations

Patrick F. O’Rourke, Scott D. Ramsey, Brian A. Temple

Nuclear Science and Engineering / Volume 196 / Number 8 / August 2022 / Pages 943-981

Technical Paper / dx.doi.org/10.1080/00295639.2022.2035180

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

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

Nuclear Science and Engineering / Volume 196 / Number 8 / August 2022 / Pages 982-1005

Technical Paper / dx.doi.org/10.1080/00295639.2022.2038529

Modeling and Simulation of Radioactive Nanomaterials of Pb-U, Pb-Th, and Pb-Co in Water-Filled Containers for Nuclear Security Applications

Elham Gharibshahi, Miltos Alamaniotis

Nuclear Science and Engineering / Volume 196 / Number 8 / August 2022 / Pages 1006-1019

Technical Paper / dx.doi.org/10.1080/00295639.2022.2035182

Enhanced Cooling Characteristics of the Cylindrical Cooling Tube Using the Inserted Helical Wire Coil Based on Finite Element Analysis

Li-Min Jin, Shuai Wu, Tong Li, Song Xue, Jia-Hua Chen, Wan-Qian Zhu

Nuclear Science and Engineering / Volume 196 / Number 8 / August 2022 / Pages 1020-1029

Technical Note / dx.doi.org/10.1080/00295639.2022.2029676

Theoretical Analysis of Cross Sections for n+^{46,47,49,50,nat.}Ti Reactions

Xinwu Su, Yongli Xu, Yinlu Han

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1031-1047

Technical Paper / dx.doi.org/10.1080/00295639.2022.2049990

The Impulse Approximation Scattering Function and Its Use in Monte Carlo Photon Transport Simulations

Alex P. Robinson, Douglass Henderson, Luke Kersting

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1048-1072

Technical Paper / dx.doi.org/10.1080/00295639.2022.2053490

Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: ¹H, C, ^58,60Ni, ^{182,183,184,186}W, ^235,238U, ²³⁹Pu

Alex Shaw, Farzad Rahnema, Andrew Holcomb, Doug Bowen

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1073-1090

Technical Paper / dx.doi.org/10.1080/00295639.2022.2049993

Double Cascades for Purification of Reprocessed Uranium Hexafluoride from ^{232, 234, 236}U Isotopes

Valerii Palkin, Eugene Maslyukov

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1091-1100

Technical Paper / dx.doi.org/10.1080/00295639.2022.2045146

Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID

Donghao He, William Walters

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1101-1113

Technical Paper / dx.doi.org/10.1080/00295639.2022.2049991

Tsallis Divergence as Strategy for Radioactive Source Search and Location

Chen Fu, Peng Xu, Yonggang Huo, Sufen Li, Xingfu Cai

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1114-1124

Technical Paper / dx.doi.org/10.1080/00295639.2022.2052551

Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat

Peter Jansson, Martin Bengtsson, Ulrika Bäckström, Francisco Álvarez-Velarde, Dušan Čalič, Stefano Caruso, Ron Dagan, Luca Fiorito, Lydie Giot, Kevin Govers, Augusto Hernandez Solis, Volker Hannstein, Germina Ilas, Marjan Kromar, Jaakko Leppänen, Marita Mosconi, Pedro Ortego, Rita Plukienė, Arturas Plukis, Anssu Ranta-Aho, Dimitri Rochman, Linus Ros, Shunsuke Sato, Peter Schillebeeckx, Ahmed Shama, Teodosi Simeonov, Alexey Stankovskiy, Holly Trellue, Stefano Vaccaro, Vanessa Vallet, Marc Verwerft, Gašper Žerovnik, Anders Sjöland

Nuclear Science and Engineering / Volume 196 / Number 9 / September 2022 / Pages 1125-1145

Technical Paper / dx.doi.org/10.1080/00295639.2022.2053489

Nuclear Data–Induced Uncertainty of Criticality in Solid-Moderated and Solid-Reflected Cores with Highly Enriched Uranium Fuel at Kyoto University Critical Assembly

Cheol Ho Pyeon, Kota Morioka

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1147-1160

Technical Paper / dx.doi.org/10.1080/00295639.2022.2070385

Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Vertical Pipe

Alex Pegarkov, Shawn Somers-Neal, Edgar Matida, Vinh Tang, Tarik Kaya

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1161-1171

Technical Paper / dx.doi.org/10.1080/00295639.2022.2067738

Radiation Interaction Characteristics of Solutions of La(NO₃)₃.6H₂O and Sm(NO₃)₃.6H₂O in Acetone Using Compton Scattering Technique

Mohinder Singh, Akash Tondon, Bhajan Singh, B. S. Sandhu

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1172-1193

Technical Paper / dx.doi.org/10.1080/00295639.2022.2067737

Sensitivity Coefficient Evaluation of an Accelerator-Driven System Using ROM-Lasso Method

Ryota Katano, Akio Yamamoto, Tomohiro Endo

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1194-1208

Technical Paper / dx.doi.org/10.1080/00295639.2022.2067447

Lagrangian Investigation of Convective Mass Transfer of Dissolved Elements at Specimen Boundaries in a Flowing Molten Lead Loop

Khaled Talaat, Osman Anderoglu

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1209-1223

Technical Paper / dx.doi.org/10.1080/00295639.2022.2062107

Investigation of Thermohydraulic Limits on Maximum Reactor Power in LEU Plate–Fueled, Pool-Type Research Reactor

Junghyun Bae, Robert S. Bean

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1224-1235

Technical Paper / dx.doi.org/10.1080/00295639.2022.2055700

Research on a Monte Carlo Simulation Method of Neutron Coded-Aperture Imaging

Huayang Zhang, Bin Zhong, Huayun Shen, Li Cheng, Jinhong Li

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1236-1246

Technical Paper / dx.doi.org/10.1080/00295639.2022.2070386

Correlation Between IASCC Susceptibility and Magnetic Properties of Stainless Steel Irradiated with Xenon Ions

Chaoliang Xu, Xiangbing Liu, Yuanfei Li, Wangjie Qian, Wenqing Jia, Qiwei Quan, Jian Yin

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1247-1254

Technical Paper / dx.doi.org/10.1080/00295639.2022.2076484

Oil Scale Profile Detection in Oil Pipeline Based on Improved Gamma-Ray Scanning Transmission Method

Zhiqiang Chen, Jingjing Chen, Shuangbao Shu, Ziqiao Yu, Yuzhong Zhang, Xiaojie Tao, Xianli Lang

Nuclear Science and Engineering / Volume 196 / Number 10 / October 2022 / Pages 1255-1265

Technical Paper / dx.doi.org/10.1080/00295639.2022.2072660

Implementation of Resonance Upscattering Treatment in FRENDY Nuclear Data Processing System

Akio Yamamoto, Tomohiro Endo, Go Chiba, Kenichi Tada

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1267-1279

Technical Paper / dx.doi.org/10.1080/00295639.2022.2087833

Analysis of Population Control Techniques for Time-Dependent and Eigenvalue Monte Carlo Neutron Transport Calculations

Ilham Variansyah, Ryan G. McClarren

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1280-1305

Technical Paper / dx.doi.org/10.1080/00295639.2022.2091906

Adjoint Flux and Perturbation Theory of γ-Mode Eigenvalue Problem Appearing in Exponential Experiments

Yasushi Nauchi, Tetsuo Matsumura

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1306-1322

Technical Paper / dx.doi.org/10.1080/00295639.2022.2092355

Investigation of the AGN-201M Research Reactor’s Unique Dominance Ratio

Mekiel Olguin, Christopher Perfetti, Forrest Brown

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1323-1332

Technical Paper / dx.doi.org/10.1080/00295639.2022.2087831

Evaluations of the Effect of Heterogeneity in HALEU Systems Using Modified Critical Benchmarks

Joseph A. Christensen, R. A. Borrelli

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1333-1348

Technical Paper / dx.doi.org/10.1080/00295639.2022.2087832

Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another

Daniel Schappel, Kurt A. Terrani

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1349-1360

Technical Paper / dx.doi.org/10.1080/00295639.2022.2090214

TRISO SiC Failure Probability for Reactivity Initiated Accidents in High-Temperature Gas-Cooled Reactors

Carlotta G. Ghezzi, Robert F. Kile, Nicholas R. Brown

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1361-1382

Technical Paper / dx.doi.org/10.1080/00295639.2022.2097466

Silicon Solar Cells for Post-Detonation Monitoring and Gamma-Radiation Effects

Praneeth Kandlakunta, Matthew Van Zile, Lei Raymond Cao

Nuclear Science and Engineering / Volume 196 / Number 11 / November 2022 / Pages 1383-1396

Technical Paper / dx.doi.org/10.1080/00295639.2022.2091905

Conceptual Design of the Transformational Challenge Reactor

B. R. Betzler, B. J. Ade, P. K. Jain, A. J. Wysocki, P. C. Chesser, W. M. Kirkland, M. S. Cetiner, A. Bergeron, F. Heidet, K. A. Terrani

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1399-1424

Technical Paper / dx.doi.org/10.1080/00295639.2021.1996196

Transformational Challenge Reactor Safety Design and Radionuclide Retention Strategy

Alexander J. Huning, William M. Kirkland, Kurt A. Terrani

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1425-1441

Technical Paper / dx.doi.org/10.1080/00295639.2021.1989237

Analysis of Postulated Accident Scenarios for the Transformational Challenge Reactor

Aaron Wysocki, Prashant Jain, Santosh Bhatt, Jordan Rader

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1442-1463

Technical Paper / dx.doi.org/10.1080/00295639.2022.2027176

Serpent and MCNP Calculations of the Energy Deposition in the Transformational Challenge Reactor

A. Talamo, A. Bergeron, S. Mohanty, S. N. P. Vegendla, F. Heidet, B. Ade, B. R. Betzler, K. Terrani

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1464-1475

Technical Paper / dx.doi.org/10.1080/00295639.2021.1977078

Design Optimization of the Transformational Challenge Reactor Outlet Plenum

N. D. See, S. Cetiner, B. R. Betzler

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1476-1495

Technical Paper / dx.doi.org/10.1080/00295639.2021.2011571

Coolant Channel Design for Additively Manufactured Reactor Cores

Justin Weinmeister, Casey J. Jesse, Prashant Jain, Brian J. Ade, Danny Schappel

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1496-1516

Technical Paper / dx.doi.org/10.1080/00295639.2022.2096999

Ordered Particle Packing in Dense TRISO/SiC Fuel Elements and Preliminary Assessment of Neutronic and Thermomechanical Characteristics

Brian J. Ade, Daniel P. Schappel, Benjamin R. Betzler, Grant W. Helmreich, Alberto Talamo, Dylan D. Richardson, Michael P. Trammel, Brian P. Jolly, Austin T. Schumacher, Kurt A. Terrani

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1517-1538

Technical Paper / dx.doi.org/10.1080/00295639.2022.2049995

Reactor Physics Considerations for Use of Yttrium Hydride Moderator

Brian J. Ade, Benjamin R. Betzler, Joseph R. Burns, Christopher W. Chapman, Jianwei Hu

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1539-1558

Technical Paper / dx.doi.org/10.1080/00295639.2022.2035157

Gradient-Informed Design Optimization of Select Nuclear Systems

John Pevey, Briana Hiscox, Austin Williams, Ondřej Chvála, Vladimir Sobes, J. Wesley Hines

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1559-1571

Technical Paper / dx.doi.org/10.1080/00295639.2021.1987133

Ex-Core Thermofluidic Optimization for Transformational Challenge Reactor

Prasad Vegendla, A. Bergeron, S. Mohanty, A. Talamo, F. Heidet, B. Ade, B. R. Betzler

Nuclear Science and Engineering / Volume 196 / Number 12 / December 2022 / Pages 1572-1580

Technical Note / dx.doi.org/10.1080/00295639.2022.2123195