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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jun 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Jump to:
Simulation of the NuScale SMR and Investigation of the Effect of Load-Following on Component Lifetimes
Una Baker, Marisol Garrouste, Sooyoung Choi, Gabriel J. Soto, Ross Snuggerud, Brendan Kochunas, Ben Lindley
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 1-22
Research Article | doi.org/10.1080/00295450.2023.2216973
Optimizing the Implementation of Small Modular Reactors into Ontario’s Future Energy Mix
C. Colterjohn, S. Nagasaki, Y. Fujii
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 23-45
Research Article | doi.org/10.1080/00295450.2023.2217390
Experimental Simulation of Decay Heat of Corium at the Lava-B Test-Bench
M. K. Bekmuldin, М. K. Skakov, V. V. Baklanov, А. V. Gradoboev, A. S. Akayev, K. O. Toleubekov
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 46-54
Research Article | doi.org/10.1080/00295450.2023.2226539
Estimation Method for Residual Sodium Amount on Unloaded Dummy Fuel Assembly
Munemichi Kawaguchi, Yasushi Hirakawa, Yusuke Sugita, Yutaka Yamaguchi
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 55-71
Research Article | doi.org/10.1080/00295450.2023.2214261
Validation and Neutronic Analysis of the CENM TRIGA MARK II SCALE Research Reactor Model: Computations Versus Experiment
H. Ziani, T. El Bardouni, C. Elyounoussi, I. Berriban, T. El Ghalbzouri, B. El Bakkari, O. El Hajjaji, S. ElMaliki ElHlaibi, M. Lahdour, H. El Yaakoubi
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 72-83
Research Article | doi.org/10.1080/00295450.2023.2216452
Examination of Deep Learning Algorithm for Nuclear Proliferation Risk Modeling
Philseo Kim, Man-Sung Yim, Justin V. Hastings, Philip Baxter
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 84-99
Research Article | doi.org/10.1080/00295450.2023.2218241
Sequential Deployment of Mobile Radiation Sensor Network Using Reinforcement Learning in Radioactive Source Search
Siyao Gu, Miltiadis Alamaniotis
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 100-111
Research Article | doi.org/10.1080/00295450.2023.2226914
Detecting Anomalies in Simulated Nuclear Data Using Autoencoders
Pedro Mena, R. A. Borrelli, Leslie Kerby
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 112-125
Research Article | doi.org/10.1080/00295450.2023.2214257
Optimized FSF Controller for Bulk Power Control of Large-Core PHWRs
P. D. Vaswani, P. K. Tamboli, Debraj Chakraborty
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 126-136
Research Article | doi.org/10.1080/00295450.2023.2214662
Cherenkov Glass Detectors with Wavelength Shifting Fibers for Neutron Measurements
Hattan Natto, Haori Yang
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 137-146
Research Article | doi.org/10.1080/00295450.2023.2217058
Performance Evaluation of Batchwise Multistage Countercurrent Extraction in a LiCl–KCl/Cd System to Separate Actinides from Rare Earth Fission Products
Yoshiharu Sakamura
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 147-164
Research Article | doi.org/10.1080/00295450.2023.2216974
One-Dimensional Steady-State Thermal Model of CNTP Reactor
Jacob Keese, D. Keith Hollingsworth
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 165-179
Research Article | doi.org/10.1080/00295450.2023.2216989
Geant4 Extension for Neutronic Calculation of Nuclear Reactor Core
Hossein Hashemi-Jozani, Khalil Moshkbar-Bakhshayesh, Soroush Mohtashami, Behzad Rokhbin
Nuclear Technology | Volume 210 | Number 1 | January 2024 | Pages 180-188
Note | doi.org/10.1080/00295450.2023.2224131
P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments
V. D’Ambrosi, J. Sercombe, S. Bejaoui, A. Chaieb, B. Baurens, R. Largenton, A. Ambard, B. Boer, G. Bonny, M. Ševeček, L. E. Herranz, F. Feria Marquez, K. Inagaki, H. Ohta, F. Boldt, J. Sappl, R. Armstrong, A. Mohamad, Y. Udagawa, C. Cozzo, J. Klouzal, M. Vitezslav, J. Corson, J. Peltonen
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 189-215
Research Article | doi.org/10.1080/00295450.2023.2194270
The UO2 Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program
G. Bonny, P. Blanpain, D. Rozzia, S. Billiet, M. Verwerft, B. Boer
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 216-231
Research Article | doi.org/10.1080/00295450.2023.2264505
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code CYRANO3
A. Chaieb, R. Largenton, A. Ambard, B. Baurens, M. Ton That
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 232-244
Research Article | doi.org/10.1080/00295450.2023.2232664
Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code
Afiqa Mohamad, Yutaka Udagawa
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 245-260
Research Article | doi.org/10.1080/00295450.2023.2185061
Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1
James Corson, Alice Chung, Steven Muller
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 261-268
Research Article | doi.org/10.1080/00295450.2023.2181042
2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE
J. Sercombe, V. D’Ambrosi, S. Béjaoui, I. Zacharie-Aubrun
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 269-284
Research Article | doi.org/10.1080/00295450.2023.2188138
Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE
V. D’Ambrosi, J. Sercombe, S. Béjaoui, I. Zacharie-Aubrun, C. Introïni, J. Karlsson, D. Jädernäs, H.-U. Zwicky
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 285-307
Research Article | doi.org/10.1080/00295450.2023.2253660
Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications
Kenta Inagaki
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 308-323
Research Article | doi.org/10.1080/00295450.2023.2239041
Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code
D. Rozzia, G. Bonny, S. Billiet, B. Boer, M. Verwerft
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 324-353
Research Article | doi.org/10.1080/00295450.2023.2229186
Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule
A. Fayet, S. Béjaoui, T. Cadiou, J. Perez-Manes, E. Deveaux, A. Vernier, V. D’Ambrosi, J. Sercombe, C. Nonon-Solaro, G. Bignan, C. Koren, S. Mimouni, A. Ambard, B. Rossaert, P. Gouat, B. Boer, R. Wouter-Bosch
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 354-377
Research Article | doi.org/10.1080/00295450.2023.2271222
Effect of Nb Addition on Corrosion Resistance of U-6Zr Alloys
Masrukan Masrukan, M. Husna Alhasa, Maman Kartaman, Juan Carlos Sihotang
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 379-390
Research Article | doi.org/10.1080/00295450.2023.2227814
Evaluation of Corrosion Behavior of Various Fe- and Ni-Based Alloys in Molten Li2BeF4 (FLiBe)
Krishna Moorthi Sankar, James R. Keiser, Dino Sulejmanovic, Tracie M. Lowe, Preet M. Singh
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 391-408
Research Article | doi.org/10.1080/00295450.2023.2229176
A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses
Kyle Carberry, Bojan Petrovic
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 409-435
Research Article | doi.org/10.1080/00295450.2023.2229181
Availability of the Emergency Safety Electrical System of a Konvoi Nuclear Power Plant Considering Mobile Arrangements of Diesel Generators After Fukushima
D. P. Dionizio, P. L. C. Saldanha, P. F. Frutuoso E Melo, C. M. F. Lapa
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 436-456
Research Article | doi.org/10.1080/00295450.2023.2229182
Numerical Investigation into the Temperature Profile of a PHWR Channel Containing a Disassembled Fuel Bundle During a Postulated Accident Condition
Ketan Ajay, Ravi Kumar, Akhilesh Gupta
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 457-470
Research Article | doi.org/10.1080/00295450.2023.2229190
Investigation on Residual Stress in SA508/Inconel Metal/CF8A Dissimilar Welded Joint for Nuclear Steam Generator Safe End Using Different Processes
Zhifang Gao, Lei Zhao, Yongdian Han
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 471-485
Research Article | doi.org/10.1080/00295450.2023.2229602
Pore Forming Agent–Assisted Fabrication of Porous Platinum Vent Frits and Their Suitability Evaluation for Radioisotope Power Sources
G. Singh, S. G. Mohod, P. V. S. Varma, P. Purohit, D. B. Sathe, R. B. Bhatt
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 486-500
Research Article | doi.org/10.1080/00295450.2023.2232224
Preparation and Performance of a Self-Brittle Corrosive Bifunctional Detergent for Corrosive Deep Decontamination of Stainless Steel Surface Based on Controlled Polymerization by the RAFT One-Pot Method
Yutuo Wang, Yintao Li, Zhengquan Zhang, Mengqing Xiao, Changwen Chen, Yuanlin Zhou, Shanqiang Wang
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 501-510
Research Article | doi.org/10.1080/00295450.2023.2232646
Designing Nuclear Fuels with a Multi-Principal Element Alloying Approach
G. Beausoleil, J. Zillinger, L. Hawkins, T. Yao, A. G. Weiss, X. Pu, N. Jerred, D. Kaoumi
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 511-531
Research Article | doi.org/10.1080/00295450.2023.2236796
First Experimental Demonstration of the Use of a Novel Planar Segmented HPGe Detector for Gamma Emission Tomography of Mockup Fuel Rods
Vikram Rathore, Lorenzo Senis, Stefan Jarl Holm, Erik Andersson Sundén, Ane Håkansson, Mounia Laassiri, Peter Dendooven, Peter Andersson
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 532-541
Research Article | doi.org/10.1080/00295450.2023.2236882
Analysis and Preliminary Design of Primary Heat Exchanger Failure Testing Facility for Lead-Cooled Fast Reactors
Federico Hattab, Fabio Giannetti, Vincenzo Narcisi, Pierdomenico Lorusso, Filippo Bussoletti, Michael Epstein, Sung Jin Lee, Mariano Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 543-564
Research Article | doi.org/10.1080/00295450.2023.2173482
Steady-State and Transient Compliance of CIRCE-THETIS CFD Model
Manuela Profir, Vincent Moreau
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 565-578
Research Article | doi.org/10.1080/00295450.2023.2175589
The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology
M. Caramello, M. Frignani, R. Beaumont, M. Tarantino, C. Stansbury, P. Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 579-590
Research Article | doi.org/10.1080/00295450.2023.2181043
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop
Tommaso Del Moro, Fabio Giannetti, Mariano Tarantino, Pierdomenico Lorusso, Marco Caramello, Damiano Vitale Di Maio, Marin Constantin
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 591-607
Research Article | doi.org/10.1080/00295450.2023.2183025
Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration
Alessio Pesetti, Mariano Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 608-628
Research Article | doi.org/10.1080/00295450.2023.2185050
Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign
Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 629-643
Research Article | doi.org/10.1080/00295450.2023.2189892
Design and Assessment of the New CIRCE-THETIS Facility for the Development of Heavy Liquid Metal Cooled Fast Reactors
Pierdomenico Lorusso, Ivan Di Piazza, Daniele Martelli, Mariano Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 644-665
Research Article | doi.org/10.1080/00295450.2023.2189903
Westinghouse Test Facilities for Lead Fast Reactor Development
Sung Jin Lee, Michael Ickes, Jeffrey L. Arndt, Michael Epstein, Asfaq Patel, Paolo Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 666-680
Research Article | doi.org/10.1080/00295450.2023.2197667
Flow-Induced Vibration Experiment in Fuel Pin Bundle with Heavy Liquid Metal Flow: Test Section Design and Measurement Methods
I. Di Piazza, D. Martelli, C. Carrelli, T. Rovai, V. Raschioni, M. Ramacciotti, A. Spezzaneve, D. Ferretti, G. Mongiardini
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 681-691
Research Article | doi.org/10.1080/00295450.2023.2203285
Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator
P. Cioli Puviani, I. Di Piazza, R. Marinari, R. Zanino, M. Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 692-712
Research Article | doi.org/10.1080/00295450.2023.2215682
Subchannel Analysis of LFR Wire-Wrapped Fuel Bundle with RELAP5-3D
Cristiano Ciurluini, Vincenzo Narcisi, Ivan Di Piazza, Fabio Giannetti
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 713-724
Research Article | doi.org/10.1080/00295450.2023.2222248
Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment
Mariano Tarantino, Pierdomenico Lorusso, Alessio Pesetti, Ivan Di Piazza, Daniele Martelli
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 725-739
Research Article | doi.org/10.1080/00295450.2023.2226525
The Passive Heat Removal Facility: Testing and Demonstrating an Innovative Decay Heat Removal System
M. Caramello, M. Frignani, R. Beaumont, M. Tarantino, J. Liao, R. F. Wright, M. Durse, A. Wimshurst, P. Ferroni
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 740-757
Research Article | doi.org/10.1080/00295450.2023.2241731
Preliminary Characterization of Alumina-Forming Austenitic–Type Advanced Alloys as Structural Materials for LFRs
A. Meli, S. Bassini, C. Ciantelli, A. Fiore, M. Angiolini, M. Tarantino
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 758-771
Research Article | doi.org/10.1080/00295450.2023.2257547
Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh
Jung-Kun Lee, Sumin Bae, Sajib A. Dahr
Nuclear Technology | Volume 210 | Number 4 | April 2024 | Pages 772-780
Research Article | doi.org/10.1080/00295450.2023.2277027
Impact Analysis of a Commercial Airplane Over a Nuclear Spent Fuel Dry Storage Cask
Edgar Hernández-Palafox, Pablo Ruiz-López, Luis Héctor Hernández Gómez, Alejandra Armenta-Molina, Gilberto Soto-Mendoza, Juan Alfonso Beltrán-Fernández, Luis Alberto Arenas-Magos
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 781-794
Research Article | doi.org/10.1080/00295450.2023.2244314
Attractiveness of Fissile Material in Nuclear Wastes from Different Fuel Cycles
Milos I. Atz, Massimiliano Fratoni
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 795-813
Research Article | doi.org/10.1080/00295450.2023.2246736
Validation of the Hybrid Turbulence Model in Detailed Thermal-Hydraulic Analysis Code SPIRAL for Fuel Assembly Using Sodium Experiments Data of 37-Pin Bundles
Ryuji Yoshikawa, Yasutomo Imai, Norihiro Kikuchi, Masaaki Tanaka, Hiroyuki Ohshima
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 814-835
Research Article | doi.org/10.1080/00295450.2023.2249707
Construction of the Dynamic Model and Control System for the Canadian Supercritical Water–Cooled Reactor Power Plant
Huirui Han, Chao Zhang
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 836-849
Research Article | doi.org/10.1080/00295450.2023.2249710
Exhaustive Test Case Generation for Nuclear Safety Software Based on the Software Logic Model
Sang Hun Lee, Seung Jun Lee, Sung Min Shin, Eun-Chan Lee, Hyun Gook Kang
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 850-867
Research Article | doi.org/10.1080/00295450.2023.2250133
Artificial Intelligence Detection System of Radioactive Nanocomposites in Liquid-Filled Containers for Nuclear Security
Elham Gharibshahi, Miltos Alamaniotis
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 868-883
Research Article | doi.org/10.1080/00295450.2023.2254168
Evaluation of Molten Corium Spreading and Sedimentation Behaviors Within Primary Containment Vessel in Unit 3 of Fukushima Daiichi Nuclear Power Plant Toward the Best Prediction of Fuel Debris Distribution
Ryo Yokoyama, Masahiro Kondo, Shunichi Suzuki, Christophe Journeau, Marco Pellegrini, Koji Okamoto
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 884-905
Research Article | doi.org/10.1080/00295450.2023.2262255
A Semi-Empirical Correlation for the Onset of Density Wave Oscillations in a Helical Coil Steam Generator
José N. Reyes Jr.
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 906-918
Research Article | doi.org/10.1080/00295450.2023.2264475
REMADA: An Emergency Decision-Making Software for Radiation Dose Estimation of Mitigation Tasks in a Reactor Building During Severe Nuclear Accidents
Chunsen Shi, Jun Li, Jianxiang Zheng, Jian Zhang, Liuxuan Cao, Huifang Miao
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 919-932
Research Article | doi.org/10.1080/00295450.2023.2264515
Comparison of Neutron Radiation Response of Conventionally Wrought Versus Additive Manufacturing Production Methods in Alloy 625
V. O’Donnell, X. He, T. Keya, G. Harvill, M. Andurkar, B. C. Prorok, S. M. Thompson, J. Gahl
Nuclear Technology | Volume 210 | Number 5 | May 2024 | Pages 933-940
Note | doi.org/10.1080/00295450.2023.2262265
Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle
Xuyao Geng, Jie Wang
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 941-957
Research Article | doi.org/10.1080/00295450.2023.2273146
Boiling and Drying Accident of High-Level Liquid Waste in a Reprocessing Plant: Examination of the Time-Dependent Temperature Increase of the Waste and of the Generation Rates of the Individual Components Released into the Gas Phase
Takashi Kodama, Hiroshi Kinuhata, Mikio Kumagai, Kazunori Suzuki, Shin-Itiro Hayashi, Shingo Matsuoka
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 958-984
Research Article | doi.org/10.1080/00295450.2023.2273550
CFD Modeling and Analysis of a Heat-Generating Melt Pool Under External Vessel Cooling and Top Flooding
Samyak S. Munot, Arun K. Nayak, Jyeshtharaj B. Joshi
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 985-1002
Research Article | doi.org/10.1080/00295450.2023.2273565
Development of a Surrogate System of a Plant Dynamics Simulation Model and an Abnormal Situation Identification System for Nuclear Power Plants Using Deep Neural Networks
Akiyuki Seki, Masanori Yoshikawa, Ryota Nishinomiya, Shoichiro Okita, Shigeru Takaya, Xing Yan
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1003-1014
Research Article | doi.org/10.1080/00295450.2023.2273566
Monte Carlo Perturbation Analysis of Fuel Temperature Variations in the MCNP Model of the Annular Core Research Reactor
Melissa Moreno, Danielle Redhouse, Christopher Perfetti
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1015-1026
Research Article | doi.org/10.1080/00295450.2023.2274168
Modeling Microreactor Requirements for High-Performance Computing
Alvin J. H. Lee, Lucas Wodrich, Dimitri Kalinichenko, Caleb S. Brooks, Tomasz Kozlowski
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1027-1041
Research Article | doi.org/10.1080/00295450.2023.2276999
Investigating the Impact of UV-C Radiation on the Mechanical Characteristics of Semifinished Potato Tubers Prepared from Varied Potato Cultivars
Addis Lemessa Jembere, Tomasz Jakubowski
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1042-1053
Research Article | doi.org/10.1080/00295450.2023.2291254
Issues Associated with Yellow Phase Formation and Other Disruptions in Japanese High-Level Waste Vitrification and Their Improvement
Akira Sakai, Siegfried Weisenburger, Ian L. Pegg, Shuichi Ishida
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1054-1077
Note | doi.org/10.1080/00295450.2023.2266612
Comments on the Frisch-Peierls Estimate of the Critical Mass of a Uranium Fission Bomb
J. M. Pearson
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1078-1082
Note | doi.org/10.1080/00295450.2023.2274690
TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation
Paul Hurley, Connor Pigg, Yang Liu, Tomasz Kozlowski, Juliana Pacheco Duarte
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 1083-1096
Note | doi.org/10.1080/00295450.2023.2277005
Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry
Cheng-Kai Tai, Tri Nguyen, Arsen S. Iskhakov, Elia Merzari, Nam T. Dinh, Igor A. Bolotnov
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1097-1118
Research Article | doi.org/10.1080/00295450.2023.2213286
Toward Improved Correlations for Mixed Convection in the Downcomer of Molten Salt Reactors
Tri Nguyen, Elia Merzari, Cheng-Kai Tai, Igor A. Bolotnov, Brian Jackson
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1119-1142
Research Article | doi.org/10.1080/00295450.2023.2223036
Assessment of Engineering Turbulence Models in Buoyant Diabatic Turbulent Flow
Ralph Wiser, Emilio Baglietto
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1143-1166
Research Article | doi.org/10.1080/00295450.2023.2202802
Data-Driven RANS Turbulence Closures for Forced Convection Flow in Reactor Downcomer Geometry
Arsen S. Iskhakov, Cheng-Kai Tai, Igor A. Bolotnov, Tri Nguyen, Elia Merzari, Dillon R. Shaver, Nam T. Dinh
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1167-1184
Research Article | doi.org/10.1080/00295450.2023.2185056
It’s About Time: Jet Interactions in an Asymmetrical Plenum
Wayne Strasser, Robert Kacinski, Daniel Wilson, Victor Petrov, Annalisa Manera
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1185-1211
Research Article | doi.org/10.1080/00295450.2023.2238156
Assessing the Structure-Based Turbulence Model Performance for Thermal Striping Applications Using Symmetric Jet Experiments
Monica Pham, Victor Petrov, Annalisa Manera, Emilio Baglietto
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1212-1222
Research Article | doi.org/10.1080/00295450.2023.2204989
Development of a Benchmark for Thermal Striping in Gas-Cooled Fast Reactors
John Acierno, Elia Merzari, Logan Burnett, Yue Jin, Emilio Baglietto, Hangbok Choi
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1223-1244
Research Article | doi.org/10.1080/00295450.2024.2337367
A Pressure Drop and Particle Image Velocimetry Investigation into Depressurized Loss-of-Coolant Accident Parameters Applied to Packed Beds with an Aspect Ratio of D/dp = 4.4
Stephen King, Thien Nguyen, Yassin Hassan
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1245-1257
Research Article | doi.org/10.1080/00295450.2023.2259699
Direct Numerical Simulation and Large Eddy Simulation of a 67-Pebble-Bed Experiment
David Reger, Elia Merzari, Paolo Balestra, Sebastian Schunert, Yassin Hassan, Stephen King
Nuclear Technology | Volume 210 | Number 7 | July 2024 | Pages 1258-1278
Research Article | doi.org/10.1080/00295450.2023.2218245