ANS / Publications / Journals / Nuclear Technology

Analysis of DLOFC Accident in HTR-10 Operating at Higher Temperatures

Zheng Yanhua, Zhang Han, Marek Stempniewicz

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1641-1652

Review Article / dx.doi.org/10.1080/00295450.2026.2618945

HTGR TRISO Fuel and Graphite Waste Management Strategies

Dominique Hittner, Michael A. Fütterer, Julien Havette, Dominik Muszyński, Markus Olin, Athanasia Tzelepi, Kataryna Kiegiel, Werner von Lensa, Olivier Tougait

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1653-1662

Review Article / dx.doi.org/10.1080/00295450.2025.2583046

Polish-Japanese Collaborative Design of the Research-Demo High-Temperature Gas-Cooled Reactor HTGR-POLA

Mariusz P. Dąbrowski, Hirofumi Ohashi

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1663-1672

Research Article / dx.doi.org/10.1080/00295450.2025.2562640

Thermal-Hydraulic and Neutronic Deterministic Safety Analysis for the HTGR SMR Research Demonstrator for Poland

Maciej Skrzypek, Eleonora Skrzypek, Dominik Muszyński

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1673-1683

Research Article / dx.doi.org/10.1080/00295450.2025.2582290

Fuel and Graphite Temperatures in a Micro Nuclear Reactor During a DLOFC

Charl du Toit, Wayne Boyes, Johan Slabber

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1684-1698

Research Article / dx.doi.org/10.1080/00295450.2025.2521972

Consolidation of the High-Temperature Reactor Code Package HCP: Integration of the Source Term Analysis Code System STACY

Meryll Colombet, Martin Freitag

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1699-1715

Research Article / dx.doi.org/10.1080/00295450.2026.2638711

Real-Time Simulation Optimization of the HTR-PM600S Simulator

Junlin Fang, Jun Sun, Zhe Sui

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1716-1727

Research Article / dx.doi.org/10.1080/00295450.2025.2535249

The Design and Development of the Process Radiation Monitoring System of the High Temperature Gas-Cooled Reactor (HTGR) in China

Yu Wang, Jingni Guo, Wenqian Li, Feng Yao, Jianzhu Cao, Liqiang Wei, Yujie Dong, Feng Xie

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1728-1742

Research Article / dx.doi.org/10.1080/00295450.2025.2582333

Safety Classification of Modular HTGRs Based on the IAEA SSG-30 Method

Tianyun Liu, Fubing Chen, Yanhua Zheng, Jingang Liang, Yingjie Wu, Han Zhang, Haitao Wang, Fu Li

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1743-1763

Research Article / dx.doi.org/10.1080/00295450.2025.2582254

INET’s Research on SO₂ Depolarized Electrolyzer Design and Scale-Up for Nuclear Hydrogen Production

Luyao Xie, Peng Xiao, Ru Tian, Laijun Wang, Ping Zhang, Songzhe Chen

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1764-1773

Research Article / dx.doi.org/10.1080/00295450.2025.2585671

Influences of Boundary Conditions on Pulsation Characteristics and Stability Boundary of Density Wave Oscillation

Yang Su, Xiaowei Li, Hongyi Fan, Xinxin Wu, Libin Sun

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1774-1793

Research Article / dx.doi.org/10.1080/00295450.2025.2594345

Design and Demonstration of an Additively Manufactured Integrated Pressure Limiting Structure for Insertion into a Nuclear Research Reactor

Fred A. List, Richard H. Howard, Keith Carver, Chase Joslin, Julio Ortega Rojas, Thomas Butcher, Ryan R. Dehoff

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1794-1803

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2504734

HOTMAP: A Tool for Comparing Responses from Different Conditions on an Identical Mesh

Kumar S. Mohindroo

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1804-1810

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2505807

Equivalence of the Peierls and Serber Wartime Expressions for the Critical Radius of a Fissile Isotope

Bruce Cameron Reed

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1811-1816

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2505814

Development of a 2- to 10-MeV Gamma-Ray Field Using an Fe-PE-Cd Moderator Assembly with a p-Li Neutron Source

Zixu Xu, Kazuma Aoki, Indah Rosidah, Yuri Morizane, Shigeo Matsuyama, Misako Miwa, Sho Toyama, Yamato Fujii, Tsubasa Shigyo, Shingo Tamaki, Sachie Kusaka, Yuuki Chimura, Isao Murata

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1817-1828

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2505817

Simulation of Experiments on Density Wave Oscillation and Ledinegg Instabilities in Helical-Coiled Steam Generators

Alfred Krall, Michael Zavisca, Mohsen Khatib-Rahbar, Shawn Marshall, Peter Yarsky

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1829-1854

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2506179

Experimental Performance Evaluation of Miniature Low-Area-Ratio Jet Pumps for High-Temperature Applications

Vimal K. Kotak, Samiran Sengupta, Sugilal Gopalakrishnan, Sujay Bhattacharya

Nuclear Technology / Volume 212 / Number 7 / July 2026 / Pages 1855-1877

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2507932