ANS / Publications / Journals / Nuclear Technology

A Review on the Development of Single-Moderator-Based Neutron Spectrometers

Rasito Tursinah, Sidik Permana, Zaki Su’ud, Alan Maulana, Putu Sukmabuana

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 635-644

Review Article / dx.doi.org/10.1080/00295450.2024.2361177

Nonhomogeneous Poisson Process Model for Estimating Mean Time Between Failures of the JE01-AP03 Primary Pump Implemented on the RSG-GAS Reactor

Sri Sudadiyo

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 645-660

Review Article / dx.doi.org/10.1080/00295450.2024.2352663

Safety Assessment Methodology for Transportation of Radioactive Material via Train

Manorma Kumar, Guillem Cortes Rossell

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 661-673

Review Article / dx.doi.org/10.1080/00295450.2024.2356328

Validation of McCARD Monte Carlo Calculation Code Against NAA Experiments Using Rare Earth Element Certified Reference Material Activated at JRTR

Rashdan Malkawi, Sayel Marashdeh, Kafa Al-Khasawneh, Aseel Al-Mohammad, Mahmoud Suaifan, Mohammad Omari, Majd Hawwari

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 674-689

Research Article / dx.doi.org/10.1080/00295450.2024.2346869

The Use of High-Density UN Fuel in Heat-Pipe Microreactors

Cihang Lu, Erofili Kardoulaki, Nicolas E. Stauff, Arantxa Cuadra

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 690-707

Research Article / dx.doi.org/10.1080/00295450.2024.2348732

Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities

Tyler Williams, Jason Torrie, Mark Schvaneveldt, Ranon Fuller, Greg Chipman, Devin Rappleye

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 708-724

Research Article / dx.doi.org/10.1080/00295450.2024.2348849

Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle

Trevor Melsheimer, Craig Menezes, Yassin A. Hassan

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 725-741

Research Article / dx.doi.org/10.1080/00295450.2024.2348853

Examining Low-Energy Gamma-Ray Protection of a New Cement Product as an Alternative Cementitious Material Using Geant4 Software

Muneerah A. Al-Aqeel

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 742-754

Research Article / dx.doi.org/10.1080/00295450.2024.2355405

Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model

Sinem Uzun

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 755-767

Research Article / dx.doi.org/10.1080/00295450.2024.2356331

Refueling Considerations for ⁹⁹Mo Production in a CANDU Reactor

J. Haroon, E. Nichita

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 768-776

Research Article / dx.doi.org/10.1080/00295450.2024.2357917

CHF Enhancement by γ-Fe₂O₃ Nanofluids with Pool Boiling Condition on a Downward-Facing Plane

Xintian Cai, Huai-En Hsieh, Zhibo Zhang, Shiqi Wang, Saikun Wang

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 777-789

Research Article / dx.doi.org/10.1080/00295450.2024.2361180

Numerical Study of Porous Cylindrical Containment for the Fuel Element of a Centrifugal Nuclear Thermal Rocket

Pramatha Bhat, Kendall R. Adams, Stephen J. Herring, Brad Kirkwood

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 790-806

Research Article / dx.doi.org/10.1080/00295450.2024.2361185

Investigation of Lunar Shallow Subsurface Water Content and Soil Elemental Composition via Active Neutron Detection

Huanyu Han, Xiaoyu Li, Zhi Chen

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 807-820

Research Article / dx.doi.org/10.1080/00295450.2024.2361194

Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant

Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 821-847

Research Article / dx.doi.org/10.1080/00295450.2024.2361195

Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2

Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca

Nuclear Technology / Volume 211 / Number 4 / April 2025 / Pages 848-861

Research Article / dx.doi.org/10.1080/00295450.2024.2361190