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Volume 198

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Number 1

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2178232

Number 2

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2172309

Number 3

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2199679

Number 4

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2227836

Number 5

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2229193

Number 6

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2249782

Number 7

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2024.2318837

Number 8

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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

Ragai Altamimi, Mohamed S. El-Genk

Nuclear Science and Engineering / Volume 198 / Number 8 / August 2024 / Pages 1620-1644

Research Article / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2255725

Number 9

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2280344

Number 10

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2284454

Number 11

Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 239Pu

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

Nuclear Science and Engineering / Volume 198 / Number 11 / November 2024 / Pages 2051-2068

Research Article / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2288308

Analytic Error Analysis of the Partial Derivatives Cross-Section Model—II: Numerical Results

Thomas Folk, Siddhartha Srivastava, Dean Price, Krishna Garikipati, Brendan Kochunas

Nuclear Science and Engineering / Volume 198 / Number 11 / November 2024 / Pages 2096-2119

Research Article / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2023.2295075

Number 12

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2024.2303548

 

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