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Volume 211

Number 7

A Review of the Capabilities and Gaps in Canada’s Research Reactors for Facilitating the Development and Deployment of Small Modular Reactors

Zoe Hoyda, Kirk D. Atkinson, Arthur Situm

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1347-1362

Review Article / dx.doi.org/10.1080/00295450.2024.2409589

A Review of CFD Advancements Toward Thermal-Hydraulic Analysis of Prototypical Flow Conditions in PWR Subchannels

Gulab Verma, Shobha Lata Sinha, Shashi Kant Verma, Tikendra Nath Verma

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1363-1406

Review Article / dx.doi.org/10.1080/00295450.2024.2410615

A Review of Remote Welding and Nondestructive Examination Technologies for the DOE Standard Canister

D. Devin Imholte, Nilay A. Kulkarni, Nathan L. Hofmeister, Sam J. Trost, Cody M. Bennett

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1407-1422

Review Article / dx.doi.org/10.1080/00295450.2024.2410628

Identification of Distorted Gamma-Ray Signature Patterns Using Digital Filtering and Auto-Associative Memory Implemented with a Hopfield Neural Network

Luis Valdez, Miltiadis Alamaniotis, Alexander Heifetz

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1423-1437

Research Article / dx.doi.org/10.1080/00295450.2024.2400757

Transient Current Analysis of GaN Neutron Detector Based on the SRIM and TCAD Methods

Chuanfeng Xiang, Haijun Li, Shanxue Xi, Yiyun Zhang, Chunzhi Zhou, Shanqiang Wang, Tao Sun, Xiaoyan Yi, Junxi Wang, Jinmin Li

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1438-1447

Research Article / dx.doi.org/10.1080/00295450.2024.2403887

Real-World Video Denoising for Visual Inspection in High-Dose Radiological Environments

Andrew Young, Zhouxiang Fei, Jaime Zabalza, Graeme M. West, Paul Murray, Stephen D. J. McArthur

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1448-1458

Research Article / dx.doi.org/10.1080/00295450.2024.2410610

Constitutive Modeling of Anisotropic Plasticity with ML Algorithms in Metals

K M Zaheen Nasir, Tanaya Chakma

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1459-1472

Research Article / dx.doi.org/10.1080/00295450.2024.2410620

Lumped Parameter Analysis of Autogenous Propellant Pressurization System for Nuclear Thermal Rocket

Elia Puccinelli, Valerio Giusti, Angelo Pasini

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1473-1495

Research Article / dx.doi.org/10.1080/00295450.2024.2410637

Design of Moderator Assemblies for Fast, Epithermal, or Thermal Neutron–Dominated n-γ Mixed Fields Using a D-D Neutron Source

Zixu Xu, Kazuma Aoki, Shingo Tamaki, Sachie Kusaka, Yuuki Chimura, Isao Murata

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1496-1508

Research Article / dx.doi.org/10.1080/00295450.2024.2410642

Human Factors Considerations in Artificial Intelligence Applications for Nuclear Power Plants

Torrey Mortenson, Casey Kovesdi, Jeremy Mohon

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1509-1525

Research Article / dx.doi.org/10.1080/00295450.2024.2411153

Potentiality of Nano Pb2O3–Enhanced Cement as a Nuclear Radiation Shield for Radiation Therapy Facilities

G. B. Hiremath, N. R. Banapurmath, Ashok M. Sajjan, N. H. Ayachit, N. M. Badiger

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1526-1538

Research Article / dx.doi.org/10.1080/00295450.2024.2411491

Tailoring ZrWNb-Based Refractory High Entropy Alloys: A Multidirectional Characterization Through Elemental, Physical, Thermodynamic, and Nuclear Radiation Attenuation Properties

Ömer Güler, İskender Özkul, Ghada Almisned, Duygu Sen Baykal, Hessa Alkarrani, G. Kilic, A. Mesbahi, H. O. Tekin

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1539-1561

Research Article / dx.doi.org/10.1080/00295450.2024.2411791

Investigation of Abnormal Level Control Oscillations in a BWR Feedwater System

Tat Nghia Nguyen, Roberto Ponciroli, Richard B. Vilim

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1562-1576

Research Article / dx.doi.org/10.1080/00295450.2024.2417563

Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles

Veronica V. Karriem, William J. Marshall

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1577-1589

Research Article / dx.doi.org/10.1080/00295450.2024.2421676

Nuclear Data Uncertainty Propagation in the PWR MOX/UO2 Core Transient Benchmark

Shigeki Shiba

Nuclear Technology / Volume 211 / Number 7 / July 2025 / Pages 1590-1607

Note / dx.doi.org/10.1080/00295450.2024.2421671