Full-scale neutronic/thermal–hydraulic coupling analysis of plate-type reactor based on RMC and MOOSE

J Chen, G Liu, S Huang, Y He, M Qiu, K Wang… - Progress in Nuclear …, 2024 - Elsevier
In this paper, a three-dimensional full-scale neutronic/thermal–hydraulic coupled analysis
for the plate-type reactor is proposed based on the Multiphysics Object-Oriented Simulation …

Highly-detailed neutronic and thermal-hydraulic coupled calculations for OPAL reactor using diverse codes and approaches

D Ferraro, I Ferrari, A Doval, E Villarino… - Nuclear Engineering and …, 2024 - Elsevier
The industry-standard approach for designing and operating research reactors cores relies
on well-established methodologies that consider uncoupled neutronic calculations and a …

[HTML][HTML] Elasto-plastic phase-field analysis of thermal induced-cracking and its application towards metal additive manufacturing

R Darabi, E Azinpour, A Reis, JC de Sa - European Journal of Mechanics-A …, 2024 - Elsevier
Abstract Metal Additive Manufacturing (MAM) technology has evolved significantly,
transitioning from its initial role in rapid prototyping to becoming a pivotal component in …

A preliminary study on the blistering behavior of dispersion plate-type fuel assembly

S Yu, K Zhang, Y Yang, Y Liu, W Tian, S Qiu, J Xu… - Annals of Nuclear …, 2025 - Elsevier
The dispersion plate fuel assembly, owing to its favorable characteristics of low temperature
gradient, high stability, and excellent thermal conductivity, has become a focal point in the …

Multi-physics analysis of SBLOCA by coupled Neutronics/Thermal-Hydraulics full plant model

M Ghafari, N Vosoughi - Nuclear Engineering and Design, 2024 - Elsevier
With the development of computational tools, the accident analysis would be performed by
best estimate approaches. The employment of multi-physics codes would be considered as …

[HTML][HTML] 板状燃料富集度对燃料性能的影响研究

岳智瑛, 贺亚男, 刘洪权, 巫英伟, 章静… - NUCLEAR …, 2024 - opticsjournal.net
摘要核燃料的富集度对燃料性能有着重要的影响. 为探究燃料富集度对U 3 Si 2-Al
板状燃料性能的影响, 本研究基于BEEs-Plates/OpenMC/ZEBRA 耦合程序, 针对15%, 20 …

[HTML][HTML] 压水堆棒状燃料氧化与吸氢模型开发及验证

陈楠, 向烽瑞, 贺亚男, 巫英伟, 章静… - NUCLEAR …, 2024 - opticsjournal.net
摘要核反应堆长期运行过程中, 锆合金包壳与冷却水接触会发生氧化反应, 吸氢脆化行为,
使包壳的导热性能和力学性能恶化, 威胁燃料元件的安全特性. 因此, 开展棒状燃料氧化与吸氢 …