ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Jump to:
Application of Accelerator Beam Dumps for Dark Matter Searches
Patrick Achenbach, Mirco Christmann
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 1-6
Research Article | doi.org/10.1080/00295639.2022.2151301
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities
Ahmed Badruzzaman
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 7-30
Research Article | doi.org/10.1080/00295639.2023.2177073
The HighNESS Project at the European Spallation Source: Current Status and Future Perspectives
V. Santoro, K. H. Andersen, P. Bentley, M. Bernasconi, M. Bertelsen, Y. Beßler, A. Bianchi, T. Brys, D. Campi, A. Chambon, V. Czamler, D. D. Di Julio, E. Dian, K. Dunne, M. J. Ferreira, P. Fierlinger, U. Friman-Gayer, B. T. Folsom, A. Gaye, G. Gorini, C. Happe, M. Holl, Y. Kamyshkov, T. Kittelmann, E. B. Klinkby, R. Kolevatov, S. I. Laporte, B. Lauritzen, J. I. Marquez Damian, B. Meirose, F. Mezei, D. Milstead, G. Muhrer, V. Neshvizhevsky, B. Rataj, N. Rizzi, L. Rosta, S. Samothrakitis, H. Schober, J. R. Selknaes, S. Silverstein, M. Strobl, M. Strothmann, A. Takibayev, R. Wagner, P. Willendrup, S. Xu, S. C. Yiu, L. Zanini, O. Zimmer
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 31-63
Research Article | doi.org/10.1080/00295639.2023.2204184
Design and Development of the 200-kW Beam Dump
Huan Jia, Haihua Niu, Han-Jie Cai, Chenzhang Yuan, Xunchao Zhang, Yuanshuai Qin, Hongming Xie, Baifan Wang, Peng Zhang, Yuxuan Huang, Tieming Zhu, Tianji Peng, Weilong Chen, Qingwei Chu, Jianqiang Wu, Shenghu Zhang, Xiang Li, Duanyang Jia, Bin Zhang, Yuan He, Hongwei Zhao, Wenlong Zhan
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 64-73
Research Article | doi.org/10.1080/00295639.2022.2164149
Advances in Nuclear Data and Software Development for the HighNESS Project
Kemal Ramić, J. I. Marquez Damian, D. D. Di Julio, T. Kittelmann, D. Campi, M. Bernasconi, A. Gosh, G. Gorini, N. Rizzi, E. Klinkby, V. Santoro
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 74-82
Research Article | doi.org/10.1080/00295639.2023.2184196
A High-Throughput Hot Surface Ion Source for Electromagnetic Radioisotope Separation
Peter Norgard, Bradley D. Jeffries, Barry Higgins, John M. Gahl, J. David Robertson
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 83-91
Research Article | doi.org/10.1080/00295639.2023.2173965
Benchmarking of the NCrystal SANS Plugin for Nanodiamonds
Nicola Rizzi, Jose I. Marquez Damian, Thomas Kittelmann, Bent Lauritzen, Esben Klinkby, Quentin Estiez, Valentina Santoro
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 92-100
Research Article | doi.org/10.1080/00295639.2023.2196926
Ionization Efficiency Measurement and Optimization of a Thermal Ion Source for Radioisotope Electromagnetic Separation
Bradley D. Jeffries, Peter Norgard, Barry Higgins, John M. Gahl
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 101-108
Research Article | doi.org/10.1080/00295639.2023.2194198
Influence of Particle Beam and Accelerator Type on ADS Efficiency
M. Paraipan, V. M. Javadova, S. I. Tyutyunnikov
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 109-120
Research Article | doi.org/10.1080/00295639.2023.2175582
Development of Tracer Particles for Positron Emission Particle Tracking
Thomas Leadbeater, Andy Buffler, Michael van Heerden, Ameerah Camroodien, Deon Steyn
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 121-137
Research Article | doi.org/10.1080/00295639.2023.2171234
Photoproton Production of 99mTc and Its Theranostic Counterpart 101Tc via (γ,p) Reaction on Ruthenium
A. Tsechanski, D. Fedorchenko, V. Starovoitova
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 138-144
Research Article | doi.org/10.1080/00295639.2023.2205816
Effects of Carbon on Void Nucleation in Self-Ion–Irradiated Pure Iron
Zhihan Hu, Lin Shao
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 145-157
Research Article | doi.org/10.1080/00295639.2023.2224468
Photon Activation Analysis in Gallium, Nickel, and Vanadium
Robert Bentley, Geno Santistevan, Douglas Wells, Andrew Hutton, Adam Stavola, Steve Benson, Kevin Jordan, Joe Gubeli, Pavel Degtiarenko, Lila Dabill
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 158-166
Research Article | doi.org/10.1080/00295639.2023.2180265
Photonuclear Production of 67Cu From Gallium
G. Santistevan, R. Bentley, D. Wells, A. Hutton, A. Stavola, S. Benson, K. Jordan, J. Gubeli, P. Degtiarenko, L. Dabill
Nuclear Science and Engineering | Volume 198 | Number 1 | January 2024 | Pages 167-173
Note | doi.org/10.1080/00295639.2023.2178232
Radiological Characterization Studies for the CNGS Dismantling
Claudia Ahdida, Elzbieta Nowak, Christelle Saury, Heinz Vincke, Helmut Vincke
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 175-184
Research Article | doi.org/10.1080/00295639.2023.2204183
Current Progress in Standardization of Shielding Concrete Composition for Japanese Facility Design
Yoshihiro Hirao, Koichi Okuno, Ken-ichi Kimura, Mikihiro Nakata, Tomohiro Ogata, Yukio Sakamoto, Ken-ichi Tanaka, Koji Oishi, Satoshi Ishikawa, Masahiro Yoshida, Toshio Amano, Kazuaki Kosako, Toshinobu Maenaka
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 185-192
Research Article | doi.org/10.1080/00295639.2023.2177077
Few-View CT Image Reconstruction via Least-Squares Methods: Assessment and Optimization
Mónica Chillarón Pérez, Vicente E. Vidal, Gumersindo J. Verdú, Gregorio Quintana-Ortí
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 193-206
Research Article | doi.org/10.1080/00295639.2023.2199677
Estimation of 137Cs Contamination Density of Wall, Ceiling, and Floor at Unit 2 Operation Floor in Fukushima Daiichi Nuclear Power Station Using Pinhole Gamma Camera
Katsumi Hayashi, Hideo Hirayama, Kohei Iwanaga, Kenjiro Kondo, Seishiro Suzuki
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 207-227
Research Article | doi.org/10.1080/00295639.2023.2204974
Estimated 137Cs Radioactivity in the Gap Between the Top and Middle Covers at a Shield Plug in the Fukushima Daiichi Nuclear Power Station Unit 2
Hideo Hirayama, Kohei Iwanaga, Katsumi Hayashi, Kenjiro Kondo, Seishiro Suzuki, Zenko Yoshida
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 228-244
Research Article | doi.org/10.1080/00295639.2023.2227824
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case
Anna Cimmino, Veronika Olšovcová, Roberto Versaci, Dávid Horváth, Benoit Lefebvre, Andrea Tsinganis, Vojtěch Stránský, Roman Truneček, Zuzana Trunečková
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 245-263
Research Article | doi.org/10.1080/00295639.2023.2191585
MLEM Neutron Spectra Unfolding in a Radiotherapy Bunker Using Bonner Sphere Spectrometer
S. Oliver, S. Morató, B. Juste, R. Miró, G. Verdú, N. Tejedor, J. Pérez-Calatayud
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 264-273
Research Article | doi.org/10.1080/00295639.2023.2192312
Current Status of TRIPOLI-4® Monte Carlo Radiation Transport Code on Adult and Pediatric Computational Phantoms for Radiation Dosimetry Study
Yi-Kang Lee, François-Xavier Hugot
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 274-286
Research Article | doi.org/10.1080/00295639.2023.2197856
Source Nuclide Density First-Order and Second-Order Sensitivities in Monte Carlo Codes
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 287-299
Research Article | doi.org/10.1080/00295639.2022.2161279
Sensitivity Analysis in Coupled Monte Carlo Radiation Transport Simulations
Christopher Perfetti, Brian Franke, Ron Kensek, Aaron Olson
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 300-310
Research Article | doi.org/10.1080/00295639.2023.2184192
Early-Stage Radiation Safety Analysis for the Spallation Neutron Source Second Target Station Bunker Operations
Kumar S. Mohindroo, Thomas Miller, Igor Remec
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 311-318
Research Article | doi.org/10.1080/00295639.2023.2191584
Comparison of the TRIPOLI-4®, DIANE, and MCNP6 Monte Carlo Codes on the Barber & George Benchmark for Photonuclear Reactions
Tran Kim Tuyet, Alexis Jinaphanh, Cédric Jouanne, Frédéric Gérardin, Sébastien Lemaire, Andrea Zoia
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 319-335
Research Article | doi.org/10.1080/00295639.2023.2195925
Benchmark Experiments for Bulk and Maze Shielding Using Activation Detectors with 24-GeV/c Protons at CERN/CHARM
Noriaki Nakao, Toshiya Sanami, Tsuyoshi Kajimoto, Robert Froeschl, Davide Bozzato, Elpida Iliopoulou, Angelo Infantino, Hiroshi Yashima, Eunji Lee, Takahiro Oyama, Masayuki Hagiwara, Seiji Nagaguro, Tetsuro Matsumoto, Akihiko Masuda, Yoshitomo Uwamino, Stefan Roesler, Markus Brugger
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 336-347
Research Article | doi.org/10.1080/00295639.2023.2196228
Estimation of Absorbed Dose due to Gas Bremsstrahlung Based on Residual Gas in Electron Storage Rings
Akihiro Takeuchi, Masayuki Hagiwara, Hiroki Matsuda, Toshiro Itoga, Hiroyuki Konishi
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 348-357
Research Article | doi.org/10.1080/00295639.2023.2211197
Benchmarking of Proton- and Neutron-Induced Nuclear Data with MCNP6.2 Using SINBAD Experiments
Yurdunaz Celik, Yosuke Iwamoto, Alexey Stankovskiy, Maureen Ciccarelli, Gert van den Eynde
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 358-369
Research Article | doi.org/10.1080/00295639.2023.2219823
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE
Kristel Ghoos, Tucker McClanahan, Lukas Zavorka, Igor Remec
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 370-380
Research Article | doi.org/10.1080/00295639.2023.2233858
Consistency Among the Results of the ASPIS Iron88, PCA Replica, and PCA ORNL Benchmark Experiments
Ivan A. Kodeli, Steven van der Marck
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 381-390
Research Article | doi.org/10.1080/00295639.2023.2199673
Dismantling and Clearance Approach for the Swiss Light Source (SLS)
Roman Galeev, Nick Walter, Eike Hohmann, Sabine Mayer
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 391-398
Research Article | doi.org/10.1080/00295639.2023.2205041
Benchmarking of Stainless Steel Cube Neutron Leakage in Research Center Rez
Michal Kostal, Zdeněk Matěj, Martin Schulc, Evžen Losa, Jan Šimon, Evžen Novák, František Cvachovec, Vaclav Přenosil, Filip Mravec, Tomáš Czakoj, Vojtěch Rypar, Andrej Trkov, Roberto Capote
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 399-410
Research Article | doi.org/10.1080/00295639.2023.2206770
Design of Temporary Beam Stops and Bunker Wall Plugs at ESS
Amalia Chambon, Luca Zanini
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 411-422
Research Article | doi.org/10.1080/00295639.2023.2194202
Prompt Radiation Dose Analysis Within the European Spallation Source Connection Cell
Thomas M. Miller
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 423-434
Research Article | doi.org/10.1080/00295639.2023.2208648
Second Target Station Bunker Shielding with Populated and Unpopulated Neutron Beamlines: Preliminary Design
Thomas M. Miller, Paul Mueller, Kumar Mohindroo, Igor Remec
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 435-450
Research Article | doi.org/10.1080/00295639.2023.2181027
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration
Ahmad M. Ibrahim, Tucker C. McClanahan, Igor Remec
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 451-460
Research Article | doi.org/10.1080/00295639.2023.2209681
Monte Carlo Study of an Electron-Based Neutron Source for Bragg Edge Imaging
Mahdi Bakhtiari, Nam-Suk Jung, Wooyong Um, Hee-Seock Lee
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 461-475
Research Article | doi.org/10.1080/00295639.2022.2162791
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code
Odile Petit, Yannick Pénéliau, Yi-Kang Lee
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 476-485
Research Article | doi.org/10.1080/00295639.2023.2194209
Radiological Characterization with a Fluence Conversion Coefficients–Based Method: A Practical Example of the Preparatory Studies to the Pilot Beam at the CERN Large Hadron Collider
Davide Bozzato, Robert Froeschl
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 486-496
Research Article | doi.org/10.1080/00295639.2023.2211191
Generation of Optimal Weight Values Based on the Recursive Monte Carlo Method for Use in Monte Carlo Deep Penetration Calculations
Pratibha Yadav, Reuven Rachamin, Jörg Konheiser, Silvio Baier
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 497-507
Research Article | doi.org/10.1080/00295639.2023.2211199
Virtual Reality System for Monte Carlo Transport Simulation Codes Using Web Technology and Commodity Devices
Seiki Ohnishi
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 508-516
Computer Code Abstract | doi.org/10.1080/00295639.2023.2177078
Effect of Photonuclear Reactions on the Photon Deep Penetration Problem for Buildup Factor Calculation
Seiki Ohnishi, Fumiyoshi Nobuhara, Yoshihiro Hirao
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 517-526
Note | doi.org/10.1080/00295639.2023.2172309
Generational Variance Reduction in Monte Carlo Criticality Simulations as a Way of Mitigating Unwanted Correlations
Kévin Fröhlicher, Eric Dumonteil, Loïc Thulliez, Julien Taforeau, Mariya Brovchenko
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 527-544
Research Article | doi.org/10.1080/00295639.2023.2193089
High-Fidelity Transient Analysis with STREAM Based on the Predictor-Corrector Quasi-Static Method
Anisur Rahman, Hyun Chul Lee, Deokjung Lee
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 545-564
Research Article | doi.org/10.1080/00295639.2023.2194219
Continuous-Energy Time-Dependent Coarse Mesh Transport (COMET) Method for Kinetics Calculations
Dingkang Zhang, Farzad Rahnema
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 565-577
Research Article | doi.org/10.1080/00295639.2023.2196935
Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code
Faouzi Hakimi, Claude Brayer, Amandine Marrel, Fabrice Gamboa, Benoît Habert
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 578-591
Research Article | doi.org/10.1080/00295639.2023.2197838
A Novel Hybrid Deterministic and Monte Carlo Neutron Transport Formulation and Algorithm (tRAPID) for Accurate and Fast 3-D Reactor Kinetics
Valerio Mascolino, Alireza Haghighat
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 592-627
Research Article | doi.org/10.1080/00295639.2023.2197844
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations
Farzad Rahnema, Dingkang Zhang
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 628-639
Research Article | doi.org/10.1080/00295639.2023.2204820
Propagation of Uncertainties due to Nuclear Data for the LCT086 Reactor System
G. P. Nyalunga, V. V. Naicker
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 640-657
Research Article | doi.org/10.1080/00295639.2023.2205198
Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores
Naoto Aizawa, Cheol Ho Pyeon
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 658-672
Research Article | doi.org/10.1080/00295639.2023.2212580
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety
Jeongwon Seo, Hany S. Abdel-Khalik, Ugur Mertyurek, Goran Arbanas, William Marshall, William Wieselquist
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 673-701
Research Article | doi.org/10.1080/00295639.2023.2211202
Resonance Scattering Treatment with the Windowed Multipole Formalism
Gavin Ridley, Benoit Forget, Timothy Burke
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 702-726
Research Article | doi.org/10.1080/00295639.2023.2204810
Rapid Quenching of Molten Salts as an Approach for the Coordination Characterization of Corrosion Products
Juho Lehmusto, J. Matthew Kurley, III, Ercan Cakmak, James R. Keiser, Daniel Lindberg, Markus Engblom, Bruce A. Pint, Stephen S. Raiman
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 727-734
Research Article | doi.org/10.1080/00295639.2023.2204175
CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model
Samyak S. Munot, Arun K. Nayak
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 735-748
Research Article | doi.org/10.1080/00295639.2023.2197015
A Method for Inhibiting Corrosion of Type 316L Stainless Steel in High-Temperature Molten Chloride Salt
Brendan D’Souza, Amanda Leong, Jinsuo Zhang
Nuclear Science and Engineering | Volume 198 | Number 3 | March 2024 | Pages 749-753
Note | doi.org/10.1080/00295639.2023.2199679
Review on the Preparation and High-Temperature Oxidation Resistance of Metal Coating for Fuel Cladding Zirconium Alloys
Ling Sun, Yuchen Xiao, Weijiu Huang, Baifeng Luan, Baoan Wu, Huiyi Tang
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 755-770
Research Article | doi.org/10.1080/00295639.2023.2219802
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron–Induced Fission of 238Pu
H. Naik, R. J. Singh, S. P. Dange, W. Jang
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 771-785
Research Article | doi.org/10.1080/00295639.2023.2224274
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of 181Ta
Shunsuke Endo, Atsushi Kimura, Shoji Nakamura, Osamu Iwamoto, Nobuyuki Iwamoto, Gerard Rovira, Yosuke Toh, Mariko Segawa, Makoto Maeda
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 786-803
Research Article | doi.org/10.1080/00295639.2023.2227826
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR
S. P. Pathak, K. Velusamy, K. Devan, V. A. Suresh Kumar
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 804-817
Research Article | doi.org/10.1080/00295639.2023.2216127
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident
I Wayan Ngarayana, Kenta Murakami, Anis Rohanda, Tatsuya Suzuki
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 818-824
Research Article | doi.org/10.1080/00295639.2023.2227829
Chromium Carbide Coatings for Inner-Side Fuel Cladding Protection: A Reactor Physics–Based Performance Analysis
Rofida H. Khlifa, Nicolay N. Nikitenkov, Viktor N. Kudiiarov
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 825-831
Research Article | doi.org/10.1080/00295639.2023.2224464
Proper Orthogonal Decomposition Mode Coefficient Interpolation: A Non-Intrusive Reduced-Order Model for Parametric Reactor Kinetics
Zachary K. Hardy, Jim E. Morel
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 832-852
Research Article | doi.org/10.1080/00295639.2023.2218581
A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes
Marco Tiberga, Simone Santandrea
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 853-897
Research Article | doi.org/10.1080/00295639.2023.2214488
Impact Assessment of Radiative Heat Transport in ARC-Class Reactor FLiBe Liquid Immersion Blanket
Gabriele Ferrero, Raffaella Testoni, Massimo Zucchetti
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 898-913
Research Article | doi.org/10.1080/00295639.2023.2219815
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations
Sooyoung Choi, Andrew Fitzgerald, Nicholas Herring, Brendan Kochunas
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 914-944
Research Article | doi.org/10.1080/00295639.2023.2224234
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations
Yousef M. Farawila, Daniel R. Tinkler
Nuclear Science and Engineering | Volume 198 | Number 4 | April 2024 | Pages 945-979
Research Article | doi.org/10.1080/00295639.2023.2227836
Deterministic Transport Calculation Method for Statistical Geometry with Small Fuel Particles
Akio Yamamoto, Tomohiro Endo, Satoshi Takeda, Hiroki Koike, Kazuya Yamaji, Koji Asano
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 981-992
Research Article | doi.org/10.1080/00295639.2023.2230414
An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations
Qi Li, Song Jiang, Wenjun Sun, Xiaojing Xu
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 993-1020
Research Article | doi.org/10.1080/00295639.2023.2230416
Neutron Importance Estimation via New Recursive Monte Carlo Method for Deep Penetration Neutron Transport
Delgersaikhan Tuya, Yasunobu Nagaya
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1021-1035
Research Article | doi.org/10.1080/00295639.2023.2233850
TRISO Burnup-Dependent Failure Analysis of a HTGR Design-Basis Accident Using BISON
Carlotta G. Ghezzi, Brian D. Wirth, Nicholas R. Brown
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1036-1050
Research Article | doi.org/10.1080/00295639.2023.2230031
Separation of Thorium from Light Rare Earth Elements from Monazite Chloride Leach Liquor
Ana Carolina Santos de Souza, Luiz Rogério Pinho de Andrade Lima
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1051-1061
Research Article | doi.org/10.1080/00295639.2023.2229600
Experimental Study of Thick Target Yield from the 13C(α,n0)16O Reaction
P. S. Prusachenko, T. L. Bobrovskiy, M. V. Bokhovko, A. F. Gurbich
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1062-1074
Research Article | doi.org/10.1080/00295639.2023.2236477
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem
Yu Yang, Helin Gong, Qiaolin He, Qihong Yang, Yangtao Deng, Shiquan Zhang
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1075-1096
Research Article | doi.org/10.1080/00295639.2023.2236840
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches
Junda Zhang, Tao Li, Zhirui Shen, Xiangyue Li, Jinbiao Xiong, Xiang Chai, Xiaojing Liu, Tengfei Zhang
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1097-1121
Research Article | doi.org/10.1080/00295639.2023.2227838
Neutronic Characterization for a Pressurized Water Reactor Spent Fuel Assembly
Rowayda Fayez M Abou Alo, Amr Abdelhady, Mohamed K. Shaat
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1122-1130
Research Article | doi.org/10.1080/00295639.2023.2227837
Simulating Properties of Canadian Research Reactor Fuels Important to Disposal
Aaron Barry, Markus H. A. Piro
Nuclear Science and Engineering | Volume 198 | Number 5 | May 2024 | Pages 1131-1154
Research Article | doi.org/10.1080/00295639.2023.2229193
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of 181Ta
Jesse M. Brown, Devin P. Barry, Robert C. Block, Amanda Youmans, Hyun Choun, Adam Ney, Ezekiel Blain, Michael J. Rapp, Yaron Danon
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1155-1165
Research Article | doi.org/10.1080/00295639.2023.2249786
Measurement of Photoneutrons from Depleted Uranium and Comparison Study Using MCNPX-PoliMi
Abbas J. Jinia, Tessa E. Maurer, Christopher A. Meert, Shaun D. Clarke, Hun-Seok Kim, David D. Wentzloff, Sara A. Pozzi
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1166-1178
Research Article | doi.org/10.1080/00295639.2023.2238169
High-Order Finite Element Second Moment Methods for Linear Transport
Samuel Olivier, Terry S. Haut
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1179-1214
Research Article | doi.org/10.1080/00295639.2023.2238171
Impact of Uncertainty Reduction on Lead-Bismuth Coolant in Accelerator-Driven System Using Sample Reactivity Experiments
Ryota Katano, Akito Oizumi, Masahiro Fukushima, Cheol Ho Pyeon, Akio Yamamoto, Tomohiro Endo
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1215-1234
Research Article | doi.org/10.1080/00295639.2023.2246779
Angular Adaptivity in P0 Space and Reduced Tolerance Solves for Boltzmann Transport
S. Dargaville, R. P. Smedley-Stevenson, P. N. Smith, C. C. Pain
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1235-1254
Research Article | doi.org/10.1080/00295639.2023.2240658
Application of the Gauss-Seidel Method to the Chebyshev Rational Approximation Method for Solving Nuclear Fuel Depletion Systems
Olin W. Calvin, Namjae Choi
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1255-1275
Research Article | doi.org/10.1080/00295639.2023.2241807
Comparison of the Baseline USL Calculation Methods for Loosely Coupled and Novel Neutronic Systems
Bobbi Riedel, Christopher M. Perfetti, Forrest B. Brown
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1276-1287
Research Article | doi.org/10.1080/00295639.2023.2249787
Analysis of the Operational and Safety Features of the In-Core Bubbling System of the Molten Salt Fast Reactor
Federico Scioscioli, Antonio Cammi, Stefano Lorenzi
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1288-1307
Research Article | doi.org/10.1080/00295639.2023.2250144
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository
Xiangyun Zhou, De’An Sun, Shixiang Hu, Weiding Zhuo, Min Lin
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1308-1319
Research Article | doi.org/10.1080/00295639.2023.2245281
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops
Ragai Altamimi, Mohamed S. El-Genk
Nuclear Science and Engineering | Volume 198 | Number 6 | June 2024 | Pages 1320-1346
Research Article | doi.org/10.1080/00295639.2023.2249782
Study of Stable Stratification in HiRJET Facility With Direct Numerical Simulation
Cheng-Kai Tai, Jiaxin Mao, Victor Petrov, Annalisa Manera, Igor A. Bolotnov
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1347-1370
Research Article | doi.org/10.1080/00295639.2023.2197656
Benchmark Experiments for Turbulent Mixing in the Scaled-Down Upper Plenum of High-Temperature Gas-Cooled Reactors Under Accident Scenario
J. Mao, S. Che, V. Petrov, A. Manera
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1371-1385
Research Article | doi.org/10.1080/00295639.2023.2186726
High-Fidelity Simulation of Mixing Phenomena in Large Enclosures
Victor Coppo Leite, Elia Merzari, Jiaxin Mao, Victor Petrov, Annalisa Manera
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1386-1403
Research Article | doi.org/10.1080/00295639.2023.2186159
Validation of RANS-Based Turbulence Models Against High-Resolution Experiments and DNS for Buoyancy-Driven Flow with Stratified Fronts
J. Mao, V. Vishwakarma, Z. Welker, C. K. Tai, I. A. Bolotnov, V. Petrov, A. Manera
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1404-1425
Research Article | doi.org/10.1080/00295639.2023.2241800
Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics
Arsen S. Iskhakov, Victor Coppo Leite, Elia Merzari, Nam T. Dinh
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1426-1438
Research Article | doi.org/10.1080/00295639.2023.2180987
Direct Numerical Simulation of Heat Transfer in a 7-Pin Wire-Wrapped Rod Bundle
Carolina Bourdot Dutra, Luiz Aldeia Machado, Elia Merzari
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1439-1454
Research Article | doi.org/10.1080/00295639.2023.2246778
High-Fidelity Simulations of Shield Assembly Mixed-Convection Flows with Applications Toward Reduced-Resolution Modeling
Adam R. Kraus, Elia Merzari, Mathieu Martin, Dustin Langewisch, Yassin Hassan
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1455-1476
Research Article | doi.org/10.1080/00295639.2023.2255463
Multiscale Modeling of Flow in Rod Bundles: From Direct Numerical Simulation and Subchannel to Coarse-Mesh CFD
Adam R. Kraus, Elia Merzari
Nuclear Science and Engineering | Volume 198 | Number 7 | July 2024 | Pages 1477-1496
Research Article | doi.org/10.1080/00295639.2024.2318837
A Precision Benchmark Suite for Nuclear Reactor Point Kinetics Equations via Converged Accelerated Taylor Series (CATS)
B. D. Ganapol
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1497-1533
Research Article | doi.org/10.1080/00295639.2023.2255727
Preliminary Conceptual Design of Nuclear Thermal Rocket Reactor Cores Using Ceramic Fuels with Beryllium or Composite Neutron Moderators
G. J. Youinou, A. Abou-Jaoudé
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1534-1565
Research Article | doi.org/10.1080/00295639.2023.2252637
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 233U
H. Naik, S. P. Dange, R. J. Singh, W. Jang
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1566-1582
Research Article | doi.org/10.1080/00295639.2023.2259746
Evaluation of Neutron Cross-Section Data Using Gaussian Mixture Model and Digital Filter
Tejashree S. Phatak, Jayalekshmi Nair, Sangeetha Prasanna Ram, B. J. Roy
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1583-1606
Research Article | doi.org/10.1080/00295639.2023.2259748
Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique
Toshihiro Yamamoto, Hiroki Sakamoto
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1607-1619
Research Article | doi.org/10.1080/00295639.2023.2266623
Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1620-1644
Research Article | doi.org/10.1080/00295639.2023.2255461
Dependency Idioms for Quantitative Human Reliability Analysis
Vincent Philip Paglioni, Katrina M. Groth
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1645-1667
Research Article | doi.org/10.1080/00295639.2023.2250159
Optimization of Personnel Work Paths During Decommissioning of Nuclear Facilities
Junhao Zhang, Weiwei Chen, Bingyu Ni, Jing Zheng, Kaixin Zhao, Wanyi Tian, Chao Jiang
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1668-1681
Research Article | doi.org/10.1080/00295639.2023.2257508
4th-Order-SENS: A Software Module for Efficient and Exact 4th-Order Sensitivity Analysis of Neutron Transport
Ruixian Fang, Dan G. Cacuci
Nuclear Science and Engineering | Volume 198 | Number 8 | August 2024 | Pages 1682-1737
Computer Code Abstract | doi.org/10.1080/00295639.2023.2255725
The Random Ray Method Versus Multigroup Monte Carlo: The Method of Characteristics in OpenMC and SCONE
Paul Cosgrove, John R. Tramm
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1739-1758
Research Article | doi.org/10.1080/00295639.2023.2270618
A Discontinuous Galerkin Finite Element Method with Physical Modal Basis for the Neutron Transport Equation on Arbitrary Polygonal Meshes
Tao Dai, Longfei Xu, Baiwen Li, Huayun Shen, Xueming Shi
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1759-1775
Research Article | doi.org/10.1080/00295639.2023.2273569
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations
Qicang Shen, Nickolas Adamowicz, Sooyoung Choi, Yuxuan Liu, Brendan Kochunas
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1776-1805
Research Article | doi.org/10.1080/00295639.2023.2270740
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations
G. B. Hiremath, V. P. Singh, N. H. Ayachit, N. M. Badiger
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1806-1816
Research Article | doi.org/10.1080/00295639.2023.2270742
Validation of a Machine Learning–Based Nuclear Forensics Methodology for the Discrimination of a Chemically Separated Plutonium Sample from Low-Enriched Uranium
Patrick J. O’Neal, Sean P. Martinson, Sunil S. Chirayath
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1817-1829
Research Article | doi.org/10.1080/00295639.2023.2271711
Study of Influences of the Level of Zr Oxidation and Volumetric Heat Generation on Heat Transfer and Crust Formation Within CANDU Corium
Mahsa Rezaee, Dijo David, Marilyn Lightstone, Stephen Tullis
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1830-1842
Research Article | doi.org/10.1080/00295639.2023.2266625
Investigations of Suction Recirculation in Primary Sodium Pump of Future Indian Fast Breeder Reactors
M. Rajendrakumar, K. Natesan, K. Devan
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1843-1873
Research Article | doi.org/10.1080/00295639.2023.2273570
Analysis of the Use of Different Backing Layer Materials in the Design of Alpha-Decay Sails for Interplanetary and Interstellar Travel
Rio Quinn
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1874-1878
Research Article | doi.org/10.1080/00295639.2023.2278931
Convergence Analysis for the CMFD Accelerated Linear Axial Expansion Transport Method Based on Fourier Analysis
Xinyu Zhou, Kun Liu, Haitao Ju, Chen Zhao, Hongbo Zhang, Bo Wang, Wenbo Zhao, Zhang Chen
Nuclear Science and Engineering | Volume 198 | Number 9 | September 2024 | Pages 1879-1899
Research Article | doi.org/10.1080/00295639.2023.2280344
Neutron Total Cross Sections of 232Th, 237Np, 235,238U, and 239Pu from 3 to 230 MeV
P. W. Lisowski, M. S. Moore, G. L. Morgan
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1901-1910
Research Article | doi.org/10.1080/00295639.2023.2284432
An Innovational Jacobian-Split Newton-Krylov Method Combining the Advantages of the Jacobian-Free Newton-Krylov Method and the Finite Difference Jacobian-Based Newton-Krylov Method
Lixun Liu, Han Zhang, Xinru Peng, Qinrong Dou, Yingjie Wu, Jiong Guo, Fu Li
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1911-1934
Research Article | doi.org/10.1080/00295639.2023.2284447
Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code
Surian Pinem, Liem Peng Hong, Wahid Luthfi, Tukiran Surbakti, Donny Hartanto
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1935-1949
Research Article | doi.org/10.1080/00295639.2023.2284433
Calculation of Thermalized Component of Neutron Spectra in a D-D Neutron Generator
Nnaemeka Nnamani
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1950-1957
Research Article | doi.org/10.1080/00295639.2023.2284453
Development of HELIOS/BIPR/PARCS/MCNP6 Computation Route for WWER RPV Neutron Fluence Analysis and Validation Against Ex-Vessel Detector Measurement Data
S. Bznuni, A. Ugujyan, A. Amirjanyan, P. Kohut
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1958-1964
Research Article | doi.org/10.1080/00295639.2023.2284438
CFD Analysis of Effects of Grid Spacer Vane on Thermal-Hydraulic Performance of Fluid in a 5×5 Fuel Channel
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1965-1983
Research Article | doi.org/10.1080/00295639.2023.2280350
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions
Husnain Murtaza, Muhammad Abdul Basit, Romana Basit, Wenxi Tian
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1984-1997
Research Article | doi.org/10.1080/00295639.2023.2284434
Feasibility of Using Mixed-Oxide Fuel for a Pressurized Water Reactor Instead of Traditional UO2 Fuel Material
Mohy Sabry, Neveen S. Abed, Ahmed Omar, Moamen G. El-Samrah, Mohamed Y. M. Mohsen
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1998-2012
Research Article | doi.org/10.1080/00295639.2023.2284441
Flux Flattening Large Heavy Water Power Reactors with Accelerator-Driven Photoneutron Source
Arief Rahman Hakim, Douglas A. Fynan
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 2013-2037
Research Article | doi.org/10.1080/00295639.2023.2280346
Quantifying Safety Significance: An In-Depth Analysis of Importance Measures in Level 1 PSA for the VVR 10-MW Water-Water Research Reactor
Rex Gyeabour Abrefah, Felix Ameyaw
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 2038-2050
Note | doi.org/10.1080/00295639.2023.2284454
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 239Pu
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2051-2068
Research Article | doi.org/10.1080/00295639.2024.2303541
Parallel Processing of Image Databases for Accelerated Morphological Analysis
Edward Goodell, Glenn Sjoden, Reid Porter, Luther McDonald IV, Kari Sentz
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2069-2079
Research Article | doi.org/10.1080/00295639.2023.2287802
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation
Thomas Folk, Siddhartha Srivastava, Dean Price, Krishna Garikipati, Brendan Kochunas
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2080-2095
Research Article | doi.org/10.1080/00295639.2023.2288308
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—II: Numerical Results
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2096-2119
Research Article | doi.org/10.1080/00295639.2024.2303544
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration
Theophile Bonnet, Hunter Belanger, Davide Mancusi, Andrea Zoia
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2120-2147
Research Article | doi.org/10.1080/00295639.2023.2288328
A Variant of the Second-Moment Method for k-Eigenvalue Calculations
Connor Woodsford, James Tutt, Jim E. Morel
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2148-2156
Research Article | doi.org/10.1080/00295639.2024.2303107
Effectiveness of Radiation Transport Variance Reduction Methods for Wide-Area Environmental Contamination Assay Applications
E. Asano, S. Dewji
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2157-2173
Research Article | doi.org/10.1080/00295639.2024.2302764
Thermal-Hydraulic Analysis of Pebble Bed High Temperature Gas-Cooled Reactor After Shutdown Based on FLUENT Software
Junbing Zhu, Tianyun Liu, Zhiyuan Ren
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2174-2189
Research Article | doi.org/10.1080/00295639.2024.2303171
Numerical Evaluation of Sodium Droplet Swarm Combustion and Its Modeling Optimization
Cheng Peng, Jian Deng, Jiang Wu
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2190-2208
Research Article | doi.org/10.1080/00295639.2023.2292930
Study on Unstructured Mesh–Based Monte Carlo/Deterministic Coupled Particle Transport Calculation Method
Hanlin Shu, Liangzhi Cao, Qingming He, Qi Zheng, Tao Dai
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2209-2229
Research Article | doi.org/10.1080/00295639.2023.2295065
Initial Verification and Validation of a New CASMO5 JENDL-5 Nuclear Data Library for Typical LWR Applications
Tomoaki Watanabe, Kenya Suyama, Kenichi Tada, Rodolfo M. Ferrer, Joshua Hykes, Charles A. Wemple
Nuclear Science and Engineering | Volume 198 | Number 11 | November 2024 | Pages 2230-2239
Note | doi.org/10.1080/00295639.2023.2295075
A Review of Neutron–Gamma-Ray Discrimination Methods Using Organic Scintillators
Imane Ahnouz, Hanan Arahmane, Rajaa Sebihi
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2241-2273
Review Article | doi.org/10.1080/00295639.2024.2316946
Some Results Concerning the Singular Solution of the Conservative Transport Equation in Spherical Geometry
R. D. M. Garcia
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2274-2290
Research Article | doi.org/10.1080/00295639.2024.2328931
Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction
Zhaoyu Liang, Ding She, Yutong Wen, Lei Shi, Zuoyi Zhang
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2291-2303
Research Article | doi.org/10.1080/00295639.2024.2311595
Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses
Sharbrenai Anise Holyk, Robert B. Hayes
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2304-2315
Research Article | doi.org/10.1080/00295639.2024.2323866
Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis
Boran Kong, Longfei Xu, Baiwen Li
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2316-2334
Research Article | doi.org/10.1080/00295639.2024.2310391
Research on Nuclear Power Plant Operational Task Complexity Assessment Method Based on Group Decision Making and Deep Learning of EEG Signals
Dongliang Zhang, Jie Wu, Kunpeng Wu, Hanming Tao
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2335-2349
Research Article | doi.org/10.1080/00295639.2024.2306105
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities
Thomas Freyman, Karen Vierow Kirkland
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2350-2367
Research Article | doi.org/10.1080/00295639.2024.2316930
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities
Feryantama Putra, Syarip, Sihana
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2368-2381
Research Article | doi.org/10.1080/00295639.2024.2306103
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig
Muhammad Ishaq, Muhammad Zaman, Muhammad Ilyas, Alam Nawaz Khan Wardag, Mansoor H. Inayat
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2382-2402
Research Article | doi.org/10.1080/00295639.2024.2328967
Verification of Griffin-Pronghorn-Coupled Multiphysics Code System Against CNRS Molten Salt Reactor Benchmark
Mustafa K. Jaradat, Namjae Choi, Abdalla Abou-Jaoude
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2403-2436
Research Article | doi.org/10.1080/00295639.2024.2306702
Optimizing the Fixed Number Detector Placement for the Nuclear Reactor Core Using Reinforcement Learning
Kai Tan, Fan Zhang
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2437-2459
Research Article | doi.org/10.1080/00295639.2024.2303542
On the Use of the Jacobian-Free Newton Krylov Method to Generate One-Group Discontinuity and Super Homogenization Factors for Full-Core Neutron Diffusion Simulations
Bailey Painter, Dan Kotlyar
Nuclear Science and Engineering | Volume 198 | Number 12 | December 2024 | Pages 2460-2479
Research Article | doi.org/10.1080/00295639.2024.2303548