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Number 1

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

Number 2

Table of Contents
Foreword: Special issue on the Power-to-Melt and Maneuverability (P2M) Simulation Exercise (Jerome Sercombe)

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

Number 3

Table of Contents

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

Number 4

Table of Contents
Foreword: Special issue on Heavy Liquid Metal–Cooled Fast Reactor Technology (Mariano Tarantino, Giacomo Grasso, Pierdomenico Lorusso, Kamil Tuček)

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

Number 5

Table of Contents

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

Number 6

Table of Contents

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

Number 7

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/d_p = 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

Number 8

Elastic, Anelastic, and Thermal Properties of P91 Steel with Microstructural Variability
Z. Miles, A. Balodhi, T. Seuaciuc-Osorio, J. J. Wall, M. Guimaraes, A. Zevalkink, S. K. Chakrapani
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1279-1294
Research Article | doi.org/10.1080/00295450.2023.2291602
Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO₂-Li₂O-ZnO-Nb₂O₅ Glass System with the Addition of Sm₂O₃
Zhigang Li, Junfeng Zhao, Yuanjie Sun, Yi Wang, Hongtao Zhao
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1295-1303
Research Article | doi.org/10.1080/00295450.2023.2294603
A Novel Communication Framework for Reduction of Staffs in Advanced MCRs of SMRs: A Prototype Development of a NLP-Based System
Taejin Kim, Donghan Yoo, Jongin Yang, Seoryong Koo, KyungTae Lim
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1304-1318
Research Article | doi.org/10.1080/00295450.2023.2295147
Irregular, Backward-Compatible PWR Assembles with More Pins to Facilitate Uprates
Ben Lindley
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1319-1335
Research Article | doi.org/10.1080/00295450.2023.2295164
Evaluation of Reaction Rate Distribution Measurement in the Prototype Fast Reactor Monju
Kazuya Ohgama, Taira Hazama, Hiroki Katagiri, Atsushi Takegoshi, Tetsuya Mouri
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1336-1353
Research Article | doi.org/10.1080/00295450.2023.2295168
Safeguards and Security for High-Burnup TRISO Pebble Bed Spent Fuel and Reactors
Charles Forsberg, Andrew Kadak
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1354-1365
Research Article | doi.org/10.1080/00295450.2023.2298157
Multicriteria Decision Making in Site Selection for Nuclear Power Plants
Berna Tuncer, Aysen D. Akkaya, M. Semih Yucemen
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1366-1391
Research Article | doi.org/10.1080/00295450.2023.2299078
Prediction of Flooding Characteristic in Pulsed Disc and Doughnut Extraction Column Using LASSO Method
Lei Jin, Hui He, Yu Zhou, Hongguo Hou, Meng Zhang, Yang Gao
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1392-1413
Research Article | doi.org/10.1080/00295450.2023.2299081
Study on Flow Characteristics of Integrated Natural Circulation Reactor Under Inclined Conditions
Haibo Lian, Shengqiang Li, Shengyao Jiang, Hongye Zhu
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1414-1426
Research Article | doi.org/10.1080/00295450.2023.2299135
Retention of Hydrogen Bubbles Generated from Water Radiolysis in Carbonate Slurry
Tatsuya Ito, Ryuji Nagaishi, Ryo Kuwano
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1427-1443
Research Article | doi.org/10.1080/00295450.2023.2299893
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister-Filling Process: Part 1
Simon Chung, Martin Stewart, Andrew Grima, Peter Wypych, Sam Moricca
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1444-1463
Research Article | doi.org/10.1080/00295450.2023.2299894
In Situ Chlorine Generation and Rare Earth Chlorination by Molten Salt Electrolysis
Mark Schvaneveldt, Tyler Williams, Ranon Fuller, Devin Rappleye
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1464-1474
Research Article | doi.org/10.1080/00295450.2023.2299908
Sorption of U(VI) on MX-80 Bentonite and Granite in Ca-Na-Cl Saline Solutions
Zhiwei Zheng, Fabiola Guido Garcia, Jianan Liu, Shinya Nagasaki, Tammy (Tianxiao) Yang
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1475-1486
Research Article | doi.org/10.1080/00295450.2023.2300900
Bentonites as Natural Sources of Thorium and Uranium
Javiera Cervini-Silva
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1487-1495
Note | doi.org/10.1080/00295450.2023.2295152
Effect of Gamma Heating on Heat Pipe–Cooled, Calcium Hydride–Moderated Core
Rei Kimura, Kazuhito Asano
Nuclear Technology | Volume 210 | Number 8 | August 2024 | Pages 1496-1502
Note | doi.org/10.1080/00295450.2023.2299899

Number 9

Table of Contents
Foreword: Selected papers from the 2022 International High-Level Radioactive Waste Management Conference (Emily Stein, Sylvia Saltzstein, Brady Hanson, Robert Howard)

An Assessment of Deep Borehole Disposal Post-Closure Safety
Dirk Mallants, Julien Bourdet, Michael Camilleri, Punjehl Crane, Claudio Delle Piane, Alec Deslandes, Dave Dewhurst, Christian Doblin, Hans-Joachim Engelhardt, Lionel Esteban, Tilman Fischer, Ema Frery, Christoph Gerber, Matthew Josh, Uli Kelka, Manoj Khanal, Laurent Langhi, Kaveh Sookhak Lari, Thomas Poulet, Matthias Raiber, Regina Sander, Mustafa Sari, Joel Sarout, Peter Schaubs, Heather Sheldon, Baotang Shen, Jingyu Shi, Julian Strand, Axel Suckow, Cornelia Wilske, Ansgar Wunderlich, Junfang Zhang
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1511-1534
Research Article | doi.org/10.1080/00295450.2023.2266609
Natural Analogue Studies in Support of Post-Closure Safety Assessment of Deep Geological Disposal
Zhenze Li, Thanh Son Nguyen, Matthew Herod, Julie Brown, Hamed Mozafarishamsi
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1535-1548
Research Article | doi.org/10.1080/00295450.2023.2240160
Assessing the Consequences of Postclosure Criticality in Spent Nuclear Fuel
Laura Price, Halim Alsaed, Eduardo Basurto, Alex Salazar, Gregory Davidson, Mathew Swinney
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1549-1566
Research Article | doi.org/10.1080/00295450.2023.2277028
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay
Teklu Hadgu, Edward Matteo, Thomas Dewers
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1567-1577
Research Article | doi.org/10.1080/00295450.2024.2304910
Modeling Geologic Waste Repository Systems Below Residual Saturation
Matthew J. Paul, Heeho D. Park, Michael Nole, Scott L. Painter
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1578-1592
Research Article | doi.org/10.1080/00295450.2023.2262294
Adsorption of Radioactive Iodine Using Nanocarbon on ETS-10 as Adsorbent
Chaithanya Balumuru, Krishnan Raja, Piyush Sabharwall, Vivek Utgikar
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1593-1601
Research Article | doi.org/10.1080/00295450.2024.2329834
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment
Milos I. Atz, Robert A. Joseph, Edward A. Hoffman
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1602-1622
Research Article | doi.org/10.1080/00295450.2023.2287307
Roadmap of Graphite Moderator and Graphite-Matrix TRISO Fuel Management Options
C. W. Forsberg
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1623-1638
Research Article | doi.org/10.1080/00295450.2024.2337311
Drying of Spent Nuclear Fuel: Considerations and Examples
Anna d’Entremont, Rebecca Smith, Christoph Rirschl, Keith Waldrop, Darrell Dunn, Robert Einziger, Robert Sindelar
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1639-1647
Research Article | doi.org/10.1080/00295450.2023.2226519
Computation of Particulate Deposition on Dry Storage Canisters
Sarah R. Suffield, Ben J. Jensen, Philip J. Jensen, William A. Perkins, Brady D. Hanson, Steven B. Ross, Christopher L. Grant, Casey J. Spitz
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1648-1657
Research Article | doi.org/10.1080/00295450.2023.2299892
Observations of Atmospheric Corrosion Testing on Heated Austenitic Stainless Steel Surfaces: Exploring the Role of Inert Dust Particulates and Seawater
R. F. Schaller, J. Snow, M. Maguire, L. Lemieux, R. M. Katona, J. Taylor, A. Knight, C. R. Bryan
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1658-1671
Research Article | doi.org/10.1080/00295450.2023.2291605
Measurement of Aerosol Transmission Through a Stress Corrosion Crack–Like Geometry
Samuel Durbin, Ramon Pulido, Philip Jones, Adrian Perales
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1672-1684
Research Article | doi.org/10.1080/00295450.2024.2302727
Package Performance Study: A Historical Perspective and Planning for a Path Forward
Laura Hay, Steven Maheras, Erica Bickford, Matthew Feldman, Douglas Ammerman
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1685-1693
Research Article | doi.org/10.1080/00295450.2023.2232988
Exploring Public Discourse About Spent Nuclear Fuel Management on Twitter
Andrew Fox, Kuhika Gupta, Joseph Ripberger, Will Livingston, Hank Jenkins-Smith
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1694-1705
Research Article | doi.org/10.1080/00295450.2023.2240185
Spatiotemporal Analyses of News Media Coverage on “Nuclear Waste”: A Natural Language Processing Approach
Matthew D. Sweitzer, Thushara Gunda
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1706-1721
Research Article | doi.org/10.1080/00295450.2023.2229566
A Sociotechnical Readiness Level Framework for the Development of Advanced Nuclear Technologies
Aditi Verma, Todd Allen
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1722-1739
Research Article | doi.org/10.1080/00295450.2024.2336355
Status of the Site Investigation and Site Selection Process for a Deep Geological Repository in Switzerland
Herwig R. Müller, Ingo Blechschmidt, Stratis Vomvoris, Tim Vietor, Maurus Alig, Matthias Braun
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1740-1747
Note | doi.org/10.1080/00295450.2023.2262298
Current Progress on the Development of the Integrated Waste Management Consent-Based Siting Process in the United States
J. Uribe, N. Saraeva, K. Petry, E. Bickford, R. Kreuzer, R. Howard
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1748-1753
Note | doi.org/10.1080/00295450.2023.2262283
Consent-Based Siting of Spent Fuel Facilities: Evidence from Nationwide U.S. Surveys
Kuhika Gupta, Hank Jenkins-Smith, Joseph Ripberger, Andrew Fox, Will Livingston
Nuclear Technology | Volume 210 | Number 9 | September 2024 | Pages 1754-1766
Note | doi.org/10.1080/00295450.2023.2232647

Number 10

Table of Contents

Review of Filtered Containment Venting System (FCVS) Eleven Years After Fukushima Accident
Jawaria Ahad, Amjad Farooq, Masroor Ahmad, Naseem Irfan, Khalid Waheed
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1767-1823
Review Article | doi.org/10.1080/00295450.2024.2302716
Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR
Annie Berens, Nicholas Meehan, Mason Fox, Isabelle Lindsay, Nicholas R. Brown
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1824-1842
Research Article | doi.org/10.1080/00295450.2024.2302723
i-LAMP: Global, Industrywide Learning Aging Management Program for Neutron-Absorber Materials in Spent Fuel Pools
Hatice Akkurt
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1843-1857
Research Article | doi.org/10.1080/00295450.2024.2302734
Methodology to Assist in Training Maneuvers of Operation of Pumps of a Nuclear Plant Using Virtual Reality
Daniel Mól Machado, Gustavo Souza Pinheiro dos Santos, Andre Cotelli do Espirito Santo, Antonio Carlos de Abreu Mól, Celso Marcelo Franklin Lapa, Claudio Henrique dos Santos Grecco
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1858-1870
Research Article | doi.org/10.1080/00295450.2024.2302740
Numerical Simulation on Dispersion of Hydrogen Leaked in Particle Layers of Glass Beads and Soil
Atsuhiko Terada, Ryuji Nagaishi
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1871-1887
Research Article | doi.org/10.1080/00295450.2024.2302747
Asymmetric Two-Step Thermosiphon for Containment Cooling of Small Modular Reactors
Sung-Jae Yi, Jin-Hwa Yang, Byong Guk Jeon, Hwang Bae, Hyun-Sik Park, Kwang-Won Seul
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1888-1900
Research Article | doi.org/10.1080/00295450.2024.2304909
Thermal and Electrical Performance Analyses of a 100-W Radioisotope Thermoelectric Generator for Space Exploration
Shiping Wei, Jin Wang, Zhixin Ma, Ming Jin, Chunjing Li, Yuan Hu
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1901-1913
Research Article | doi.org/10.1080/00295450.2024.2304911
Simulation of Readout Electronics for Nuclear Radiation Detector Using MATLAB Program
Jamal-Eddin Assaf, Zuheir Ahmad
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1914-1924
Research Article | doi.org/10.1080/00295450.2024.2304913
Temperature-Dependent Swelling in Helium Ion Irradiated Vanadium
Weiping Zhang, Yiheng Chen, Wenrui Cheng, Liping Guo, FengFeng Luo
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1925-1931
Research Article | doi.org/10.1080/00295450.2024.2304914
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor
Amitanshu Mishra, Paban Kumar Guchhait, Samiran Sengupta
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1932-1951
Research Article | doi.org/10.1080/00295450.2024.2304915
Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring
Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1952-1974
Research Article | doi.org/10.1080/00295450.2024.2304931
Characterization of a Fast Neutron Irradiation Facility Using a Stilbene Scintillation Detector
Felix Pino, Jessica C. Delgado, Matteo Polo, Erica Fanchini, Anna Selva, Joana Minga, Gianmarco Torilla, Lodovico Ratti, Sandra Moretto
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1975-1984
Research Article | doi.org/10.1080/00295450.2024.2304993
Polarization of Compton-Scattered Prompt Gamma-Ray Technique for HEU Detection at 186 keV
Athanas Mutiso, Ayodeji B. Alajo, Xin Liu
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1985-1998
Research Article | doi.org/10.1080/00295450.2024.2306109
Release Behavior of Gaseous Ruthenium Tetroxide During Heating of High-Level Liquid Waste Simulant During Simulated Accident Conditions
Naoki Yoshida, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Hitoshi Abe, Yuichi Yamane
Nuclear Technology | Volume 210 | Number 10 | October 2024 | Pages 1999-2007
Note | doi.org/10.1080/00295450.2024.2306688

Number 11

Table of Contents

Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models
Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2009-2016
Review Article | doi.org/10.1080/00295450.2024.2309599
Validation of EPG/SAG Rev. 4 of the Kuosheng Nuclear Power Plant Using the MAAP5 Code
Yu-Min Chen, Te-Chuan Wang, Min Lee
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2017-2037
Research Article | doi.org/10.1080/00295450.2024.2306693
Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals
Shekhar Kumar
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2038-2049
Research Article | doi.org/10.1080/00295450.2024.2309070
Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2050-2073
Research Article | doi.org/10.1080/00295450.2024.2309080
Effects of Impurities and Additives on Interactions of Nuclear-Grade Graphite with Molten LiF-NaF-KF
Krishna Moorthi Sankar, Preet M. Singh
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2074-2090
Research Article | doi.org/10.1080/00295450.2024.2309600
A Blowdown Critical Heat Flux Experimental Vehicle
Musa Moussaoui, Wade Marcum
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2091-2114
Research Article | doi.org/10.1080/00295450.2024.2309601
Creep Fatigue Analysis of the 316SS Monolith in the MegaPower Heat Pipe Reactor
Yong Wang, Lichuang Liang, Jun Tian, Dongchuan Su, Hui Li, Naibin Jiang
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2115-2132
Research Article | doi.org/10.1080/00295450.2024.2310902
Development of Two-Step Method for Fast Chloride MSR Neutronics
Kyra Lawson, Nicholas R. Brown
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2133-2150
Research Article | doi.org/10.1080/00295450.2024.2310911
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills
Nora Nassiri-Mofakham, Mojtaba Kakaei
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2151-2158
Research Article | doi.org/10.1080/00295450.2024.2311977
Optimization of Elliptical U-Tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method
Binqi Hao, He Zhou, Xiaofeng Li, Zu’An Wang, Shunyang Li, Pengfei Wang
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2159-2186
Research Article | doi.org/10.1080/00295450.2024.2311978
Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels
Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2187-2203
Research Article | doi.org/10.1080/00295450.2024.2312019
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks
Ryan J. Hoover, Kenji Shimada
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2204-2214
Research Article | doi.org/10.1080/00295450.2024.2312022
A Semi-Analytical Prediction Model for Fluid-Elastic Instability of a Normal Triangular Tube Array Under Transverse Flow Excitation
Gongbo Chen, Naibin Jiang
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2215-2235
Research Article | doi.org/10.1080/00295450.2024.2312023
Density Equation for Mixed Organic Solutions Containing tri-n-butyl Nitrate, n-Dodecane, Nitric Acid, and Nitrates of Heavy Metals
Shekhar Kumar
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2236-2243
Note | doi.org/10.1080/00295450.2024.2309069

Number 12

Table of Contents
Foreword: Special issue featuring papers from the NPIC&HMIT 2023 International Topical Meeting (Vivek Agarwal, Jamie Coble)

Participatory Development of Virtual Reality Training for Nuclear Power Plant Field Operators
Hanna Koskinen, Satu Pakarinen, Tomi Passi, Kristian Lukander, Jari Laarni, Tuisku-Tuuli Salonen
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2245-2256
Review Article | doi.org/10.1080/00295450.2024.2377008
Opportunities, Challenges, and Research Needs for Remote Microreactor Operations
Kaeley Stevens, Joseph Oncken, Ronald Boring, Thomas Ulrich, Megan Culler, Haydn Bryan, Jeren Browning, Izabela Gutowska
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2257-2273
Review Article | doi.org/10.1080/00295450.2024.2344903
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions
Joseph Oncken, Linyu Lin, Vivek Agarwal
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2274-2289
Review Article | doi.org/10.1080/00295450.2024.2342206
Utility and Industry Perceptions of Control Room Modernization Over the Last 10 Years
Anna Hall, Jeffrey C. Joe
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2290-2298
Research Article | doi.org/10.1080/00295450.2024.2380228
SPIDARman: System-Level Physics-Informed Detection of Anomalies in Reactor Collected Data Considering Human Errors
Ezgi Gursel, Bhavya Reddy, Katy Daniels, Jamie Baalis Coble, Mahboubeh Madadi, Vivek Agarwal, Ronald Boring, Vaibhav Yadav, Anahita Khojandi
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2299-2311
Research Article | doi.org/10.1080/00295450.2024.2338507
Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants
Bhavya Reddy, Ezgi Gursel, Katy Daniels, Anahita Khojandi, Jamie Baalis Coble, Vivek Agarwal, Ronald Boring, Vaibhav Yadav, Mahboubeh Madadi
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2312-2330
Research Article | doi.org/10.1080/00295450.2024.2372217
Explainable, Deep Reinforcement Learning–Based Decision Making for Operations and Maintenance
Ryan M. Spangler, Mahsa Raeisinezhad, Daniel G. Cole
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2331-2345
Research Article | doi.org/10.1080/00295450.2024.2377034
Network Graph Laplacian-Based Sensor Projection in System-Level Modeling of Liquid-Metal Loop
Andres Gomez, Molly Ross, Hitesh Bindra
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2346-2361
Research Article | doi.org/10.1080/00295450.2024.2361182
Forecasting the Remaining Useful Life of Filters in Nuclear Power Plants
Andrew Young, Michael Devereux, Blair Brown, Bruce Stephen, Graeme West, Stephen McArthur
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2362-2372
Research Article | doi.org/10.1080/00295450.2024.2342187
Implementing Component Degradations into a Modelica Model of an iPWR System to Develop Health Monitoring Techniques
David Anderson, Jamie Coble
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2373-2386
Research Article | doi.org/10.1080/00295450.2024.2376996
Fault Detection and Isolation in Simulated Batch Operation of Fine Motion Control Rod Drives
Ark O. Ifeanyi, Daniel Dos Santos, Abhinav Saxena, Jamie Coble
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2387-2403
Research Article | doi.org/10.1080/00295450.2024.2323260
Enhanced Video-Level Anomaly Feature Detection for Nuclear Power Plant Component Inspections Using the Latency Mechanism
Zhouxiang Fei, Callum Manning, Graeme M. West, Paul Murray, Gordon Dobie
Nuclear Technology | Volume 210 | Number 12 | December 2024 | Pages 2404-2418
Research Article | doi.org/10.1080/00295450.2024.2337282

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