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Home / Publications / Journals / Nuclear Technology / Volume 211 / Number 10

Volume 211

Number 10

Analysis of a Selected Experiment of the OSU-MASLWR Test Facility Regarding Heat Transfer in Helically Coiled Steam Generators Using AC2-ATHLET

Julia Krieger, Marco K. Koch

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2225-2238

Review Article / dx.doi.org/10.1080/00295450.2024.2377027

Development and Validation of Pattern Recognition Algorithm and Suppression Pool Flow Modeling

Giteshkumar Patel, Elina Hujala, Vesa Tanskanen, Markku Puustinen, Juhani Hyvärinen

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2239-2253

Review Article / dx.doi.org/10.1080/00295450.2024.2399986

Transient Modeling and Simulation of a Generic Stable Salt Reactor

Thanh Hua, Yan Cao, Rui Hu, David Catalan, Andrew Ballard

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2254-2265

Rapid Communication / dx.doi.org/10.1080/00295450.2024.2440233

Large-Scale Multiphysics Simulations of Small Modular Reactors Operating in Natural Circulation

Jun Fang, Dillon Shaver, Paul Romano, Elia Merzari

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2266-2277

Research Article / dx.doi.org/10.1080/00295450.2024.2380951

Parametric Analysis of the Compact and Long-Term-Operable Passive Residual Heat Removal System

Wooseong Park, Yong Hwan Yoo, Kyung Jun Kang, Yong Hoon Jeong

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2278-2291

Research Article / dx.doi.org/10.1080/00295450.2024.2397610

Toward a Better Understanding of Reflood Thermal Hydraulics: A Summary of the OECD/NEA RBHT Project

Stephen M. Bajorek, Brian Lowery, Fan-Bill Cheung, Alessandro Del Ferraro, Marco Cherubini, Alessandro Petruzzi, Jinzhao Zhang, Martina Adorni

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2292-2307

Research Article / dx.doi.org/10.1080/00295450.2024.2409585

Assessment of the Choked Flow Model of RELAP5 for Application of Inverse Quantification Methods

Pablo Osés, Jordi Freixa, Rafael Mendizábal, Miguel Sánchez-Perea

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2308-2325

Research Article / dx.doi.org/10.1080/00295450.2024.2411805

Characterization and Modeling of Gravity-Driven Flashing of Superheated Water in a Pool Heated from Below

Jimmy Martin, Pierre Ruyer, Matthieu Duponcheel, Yann Bartosiewicz

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2326-2342

Research Article / dx.doi.org/10.1080/00295450.2024.2411835

High-Fidelity Velocity and Concentration Measurements of Turbulent Buoyant Jets

Valentina Valori, Sunming Qin, Victor Petrov, Annalisa Manera

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2343-2355

Research Article / dx.doi.org/10.1080/00295450.2024.2355406

Analyses of Jet Buoyant Flow in a Multicompartment Containment Using an Open-Source Solver

Myeong-Seon Chae, Juwook Lee, Hyoung Kyu Cho, Stephan Kelm, Domenico Paladino

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2356-2371

Research Article / dx.doi.org/10.1080/00295450.2024.2362527

CFD Modeling of Aerosol Transport and Deposition Using a Drift-Flux Model

Geoffrey S. Gray, P. Madhan Kumar, Scott J. Ormiston

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2372-2385

Research Article / dx.doi.org/10.1080/00295450.2024.2365486

High-Fidelity Simulation of the Light-to-Dense Stratification Transient in the HiRJET Facility

Cheng-Kai Tai, Haomin Yuan, Elia Merzari, Igor A. Bolotnov

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2386-2403

Research Article / dx.doi.org/10.1080/00295450.2024.2382621

LES and RANS Modeling of an 84-Pin Hexagonal Rod Bundle with Spacer Grid and Experimental Validation

Adam R. Kraus, Elia Merzari

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2404-2426

Research Article / dx.doi.org/10.1080/00295450.2024.2409594

CFD Modeling of Film Condensation from a Steam-Air Mixture in Vertical Channels

Bronwyn Rempel, Geoffrey S. Gray, Scott J. Ormiston

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2427-2445

Research Article / dx.doi.org/10.1080/00295450.2024.2410612

Application Study of Adaptive Mesh Refinement Method on Unsteady Wake Vortex Analysis

Haneen Alzahrani, Kentaro Matsushita, Takaaki Sakai, Toshiki Ezure, Masaaki Tanaka

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2446-2458

Research Article / dx.doi.org/10.1080/00295450.2025.2472582

Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program

J. Liao, C. A. Stansbury, M. E. Durse, D. L. Wise, E. Tatli, T. G. Loebig, R. F. Wright, P. Ferroni, S. J. Lee, M. Epstein, M. Caramello, M. Frignani, M. Tarantino, G. Grasso, I. Di Piazza, S. Bassini, P. Lorusso, A. Antonelli, D. Martelli, A. Wimshurst, R. Watkins, G. Macpherson, D. Wilson, H. Iacovides, A. Cioncolini, J. Francis, J. Buckley

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2459-2469

Research Article / dx.doi.org/10.1080/00295450.2024.2361187

Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants

Ye Yeong Park, In Cheol Bang

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2470-2489

Research Article / dx.doi.org/10.1080/00295450.2024.2372509

Development of a New Thermal-Hydraulic Module for FRENETIC, a Code for the Multiphysics Analysis of Liquid Metal–Cooled Reactors

Antonino Lombardo, Giuseppe F. Nallo, Nicolò Abrate, Yapeng Liu, Sandra Dulla

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2490-2507

Research Article / dx.doi.org/10.1080/00295450.2024.2397189

A Demonstration of the Risk-Informed NEI 18-04 Design Evaluation Model for the Modular High-Temperature Gas Reactor

Cesare Frepoli, Robert P. Martin, Curtis L. Smith, Kurt G. Vedros

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2508-2522

Research Article / dx.doi.org/10.1080/00295450.2024.2397613

CFD Simulations of the Molten Salt Fast Reactor

François Martin, André Bergeron, Yannick Gorsse, Elsa Merle

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2523-2533

Research Article / dx.doi.org/10.1080/00295450.2024.2408967

High-Fidelity CFD Simulation of Mixed Convection and Forced Convection in a Pebble Bed Test Reactor Core

Haomin Yuan, Tri Nguyen, David Reger, Elia Merzari, John Acierno, Michael Seneca, Dezhi Dai, Dillon Shaver, Ka-Yen Yau, Giacomo Busco, Nate Salpeter, R. Brian Jackson, Etienne Demarly

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2534-2558

Research Article / dx.doi.org/10.1080/00295450.2024.2437310

Unsteady Reynolds-Averaged Navier-Stokes Simulation of Turbulent Buoyant Jets Issued into a Model HTGR Cavity with Bottom Venting

Bo Liu, Shuisheng He, Jundi He, Charles Moulinec, Juan Uribe

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2559-2576

Research Article / dx.doi.org/10.1080/00295450.2025.2492964

CFD Modeling of Lead Solidification and Natural Convection in Support of the Westinghouse Lead-Cooled Fast Reactor Development

Dean Wilson, Hector Iacovides, Emre Tatli, Paolo Ferroni, Sung Jin Lee

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2577-2594

Research Article / dx.doi.org/10.1080/00295450.2025.2525698

Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1

Marco Pellegrini, Christophe Journeau, Nathalie Seiler, Luis E. Herranz, M. García, Claus Spengler, Charlaine Bouillet, Marc Barrachin, David Luxat, Lucas Albright

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2595-2608

Research Article / dx.doi.org/10.1080/00295450.2024.2371267

Influence of Iodine Chemistry in I2 Scrubbing Modeling

Adolf Rýdl, Taizo Kanai

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2609-2619

Research Article / dx.doi.org/10.1080/00295450.2024.2425588

Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis

M. Garbarini, G. Agnello, A. Bersano, F. Gabrielli, L. Luzzi, F. Mascari

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2620-2639

Research Article / dx.doi.org/10.1080/00295450.2025.2478333

Investigation of Machine Learning Regression Techniques to Predict Critical Heat Flux Over a Large Parameter Space

Emil Helmryd Grosfilley, Gustav Robertson, Jerol Soibam, Jean-Marie Le Corre

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2640-2654

Research Article / dx.doi.org/10.1080/00295450.2024.2380580

Digitalization, Management, and Synthesis of Thermal-Hydraulic Legacy Data Using the Dynamical System Scaling

Cesare Frepoli, Stephen A. Heagy, José N. Reyes

Nuclear Technology / Volume 211 / Number 10 / October 2025 / Pages 2655-2662

Research Article / dx.doi.org/10.1080/00295450.2024.2408981

 

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