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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
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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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2021.1951063
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2021.1975479
Solution Irregularity Remediation for Spatial Discretization Error Estimation for SN Transport Solutions
Nathan H. Hart, Yousry Y. Azmy
Nuclear Science and Engineering | Volume 196 | Number 4 | April 2022 | Pages 363-378
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2022.2035180
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 241Am
Nuclear Science and Engineering | Volume 196 | Number 8 | August 2022 | Pages 982-1005
Technical Paper | 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 | 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 | 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 | 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 | 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, 182,183,184,186W, 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 | doi.org/10.1080/00295639.2022.2049993
Double Cascades for Purification of Reprocessed Uranium Hexafluoride from 232, 234, 236U Isotopes
Valerii Palkin, Eugene Maslyukov
Nuclear Science and Engineering | Volume 196 | Number 9 | September 2022 | Pages 1091-1100
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2022.2072660
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 | doi.org/10.1080/00295639.2022.2035183
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 | doi.org/10.1080/00295639.2022.2027738
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 | doi.org/10.1080/00295639.2022.2091907
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 | doi.org/10.1080/00295639.2022.2031712
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 | doi.org/10.1080/00295639.2022.2053488
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 | doi.org/10.1080/00295639.2022.2035181
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 | doi.org/10.1080/00295639.2022.2058845
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 | doi.org/10.1080/00295639.2022.2043540
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 | doi.org/10.1080/00295639.2021.1991760
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 | doi.org/10.1080/00295639.2021.2009983
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 | doi.org/10.1080/00295639.2022.2043539
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 | doi.org/10.1080/00295639.2022.2052552
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 | doi.org/10.1080/00295639.2021.2011572
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 | doi.org/10.1080/00295639.2022.2070383
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 | doi.org/10.1080/00295639.2022.2070384
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 | doi.org/10.1080/00295639.2021.2017663
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 | doi.org/10.1080/00295639.2022.2055705
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 | doi.org/10.1080/00295639.2021.2014741
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 | doi.org/10.1080/00295639.2022.2053487
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 | doi.org/10.1080/00295639.2021.2009982
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 | doi.org/10.1080/00295639.2021.2018925
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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2022.2087831
Evaluations of the Effect of Heterogeneity in HALEU Systems Using Modified Critical Benchmarks
Nuclear Science and Engineering | Volume 196 | Number 11 | November 2022 | Pages 1333-1348
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2022.2123195
