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Volume 212

Number 6

Table of Contents
Foreword: Special Issue Featuring Selected Papers from the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation, and Safety (NUTHOS-14)(Andrew Morreale, David Novog, Elia Merzari)

Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages

Ferry Roelofs, Akshat Mathur, Heleen Uitslag-Doolaard, Markus Daubner, Karsten Litfin, Julio Pacio, Yassin Hassan

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1399-1413

Research Article / dx.doi.org/10.1080/00295450.2025.2516179

Multiscale Coupled Simulation of E-SCAPE at Isothermal Conditions

Mohammed Muaaz Mohamed Dilshad Hussain, Fajar Sri Lestari Pangukir, Dirk Cornelis Visser, Marek Michal Stempniewicz, Ferry Roelofs, Julio Pacio, Katrien Van Tichelen

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1414-1433

Research Article / dx.doi.org/10.1080/00295450.2025.2588975

Study of Turbulence and Pressure Recovery in the Heat Pipe Vapor Flow Using the Spectral-Element Method

Carolina Bourdot Dutra, Tri Nguyen, Sean P. Bistany, Elia Merzari, Joshua E. Hansel

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1434-1453

Research Article / dx.doi.org/10.1080/00295450.2025.2592503

A Comparative Study of Parametric Dynamic Mode Decomposition Algorithms on Thermal-Hydraulics Case Studies

Stefano Riva, Andrea Missaglia, Carolina Introini, In Cheol Bang, Antonio Cammi

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1454-1478

Research Article / dx.doi.org/10.1080/00295450.2025.2575701

Evaluation of Physics-Informed Machine Learning Models for Liquid Entrainment During Reflood Transient Using NRC/PSU RBHT Data

Yue Jin, Fan-Bill Cheung, Stephen M. Bajorek, Andrew Ireland, Kirk Tien, Chris L. Hoxie

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1479-1496

Research Article / dx.doi.org/10.1080/00295450.2025.2525606

Improving Accuracy of a Machine Learning Approach for Forecasting Severe Accidents

Semin Joo, Yeonha Lee, Seok Ho Song, Kyusang Song, Mi Ro Seo, Sung Joong Kim, Jeong Ik Lee

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1497-1512

Research Article / dx.doi.org/10.1080/00295450.2025.2528283

System-Level Thermal-Hydraulics Analysis of the Proposed NIST Neutron Source Design

Anil Gurgen, Abdullah G. Weiss

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1513-1521

Research Article / dx.doi.org/10.1080/00295450.2025.2537575

Influence of ATF Cladding Tube Candidates on the Critical Heat Flux in a Vertical Rod Bundle During Flow Boiling of Water at Low Pressure

Nicolas Wefers, Daniel Vlček, Wilson Heiler, Stephan Gabriel, Andreas Class

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1522-1539

Research Article / dx.doi.org/10.1080/00295450.2025.2536951

Experimental Investigation of Erosion and Corrosion of Aluminized and Non-Aluminized Steels Under High-Velocity Lead Flow

Celt Llŷn Griffith, James Macdonald, Charlotte L. Baxter, John Thomas Prabhakar, Simon Middleburgh, Walter Villanueva

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1540-1552

Research Article / dx.doi.org/10.1080/00295450.2025.2583896

Experimental Validation of Modeling and Simulation Capabilities of RELAP5-TMSR with the NNCL Experimental Facility

Weiye Jia, Rui Li, Xiandi Zuo, Maosong Cheng, Fengrui Liu, Zhimin Dai

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1553-1566

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2496598

Transient Behavior of a Boiling Water Reactor–Type Offshore Floating Nuclear Power Plant During Platform Motion

Kodai Fukuda, Toru Obara

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1567-1578

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2502266

Applicability of Butler Model for Estimation of Surface Tension in Liquid Na-K-Cs Alloys

Munemichi Kawaguchi

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1579-1594

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2502272

Transient Behavior of the NuScale 250-MW(thermal) Power Module with Cr-Coated Zr Cladding During a Severe Accident

Mohammad Amer Allaf, Emile Zaccomer, Grace Ejnik, Woo Hyun Jung, Michael Corradini, Juliana Pacheco Duarte

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1595-1608

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2503034

Design of a High-Assay Low-Enriched Uranium Tri-Structural Isotropic Critical Experiment for Advanced Reactor Validation

Holly Trellue, Theresa Cutler, Erik Luther, Nick Wynne, Justin Lee, John Downey, Scott Stinson, Kristin Stolte, Rene Sanchez, Alexis Maldonado, Hannah Morbach

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1609-1622

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2504149

Applicability of JENDL-5 to Tihange Unit 2 Reactor Core Analysis

Shigeki Shiba

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1623-1639

Regular Note / dx.doi.org/10.1080/00295450.2025.2502262