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Volume 210

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2224131

Number 2

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2271222

Number 3

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2236882

Number 4

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2277027

Number 5

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2262265

Number 6

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2299899

Number 9

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2023.2232647

Number 10

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2024.2306688

Number 11

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2024.2309069

Number 12

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295450.2024.2337282

 

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