Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way
The nuclear reactor is a multi-physics and multiscale coupling system. The conditions of
high temperature and high neutron flux in the reactor pose a significant challenge to the …
high temperature and high neutron flux in the reactor pose a significant challenge to the …
Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model
S Wu, D Wang, Y Zhang, X Wu, W Tian, S Qiu… - Progress in Nuclear …, 2024 - Elsevier
A refined coating degradation model that comprehensively considers the phenomena of
coating oxidation, diffusion, reduction, and volatilization is used to evaluate the performance …
coating oxidation, diffusion, reduction, and volatilization is used to evaluate the performance …
Annular fuel behavior analysis of U3Si2 fuel and FeCrAl cladding based on multiphysics field method
Safety, efficiency and economic benefits cannot be ignored in the development of nuclear
energy. As a type of widely used fuel in nuclear reactors, solid fuel has limited potential, long …
energy. As a type of widely used fuel in nuclear reactors, solid fuel has limited potential, long …
Investigation of plate fuel performance under reactivity initiated accidents with developed multi-dimensional coupled method
A reactivity-initiated accident is a typical nuclear reactor accident during which the core
fission rate and power increase unexpectedly, making the temperature of the fuel element …
fission rate and power increase unexpectedly, making the temperature of the fuel element …
Assessing the effect of some ATF materials and uncertainties on their properties under normal operation conditions by means of the TRANSURANUS code
P Van Uffelen, A Schubert, Z Soti - Proceedings of the 23rd Pacific Basin …, 2023 - Springer
In this work, we present the first implementation of U3Si2 fuel properties in the
TRANSURANUS code. Following the short overview of the implemented fuel properties, we …
TRANSURANUS code. Following the short overview of the implemented fuel properties, we …
Analysis of gas-cooled micro modular reactor (MMR) fuel
C Deng, S Zhu, Y He, Y Wu, K He, J Zhang… - Journal of Nuclear …, 2024 - Elsevier
The gas-cooled micro modular reactor (MMR) is a novel concept with a compact fuel form
consisting of thousands of tri-isotropic fuel (TRISO) particles dispersed in a silicon carbide …
consisting of thousands of tri-isotropic fuel (TRISO) particles dispersed in a silicon carbide …
[HTML][HTML] Development and evaluation of fuel performance analysis code FuSPAC
T Cong, H Chen, C Chen, S Zhang, H Gu - International Journal of …, 2022 - Elsevier
The nuclear fuel rod should maintain self-sustainable nuclear fission, as the first safety
barrier to prevent the leakage of radioactive products. The fuel rod performance analyses …
barrier to prevent the leakage of radioactive products. The fuel rod performance analyses …
[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 …
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 …
[引用][C] Development of the Expanding Mandrel Test Facility for Investigation of Zircaloy Cladding Performance Under Loading Strain Rate Similar to Power Ramp
Y He, Y Wu, B Qiu, Z Lei, L He, Y Jiao, P Chen, W Tian… - Available at SSRN 4290949