Envisaged future for nuclear thermal-hydraulics

被引:1
|
作者
Zhang, Jinzhao [1 ]
Hassan, Yassin [2 ]
机构
[1] Tractebel ENGIE, Blvd Simon Bolivar 34-36, B-1000 Brussels, Belgium
[2] Texas A&M Univ, 3133 TAMU, College Stn, TX 77843 USA
关键词
Fuel fragmentation relocation and dispesal; Lagrangian approach; Machine learning; Multi-scale multi-physics; System thermal hydraulics; Uncertainty quantification; Verification and validation; SIMULATION;
D O I
10.1016/j.nucengdes.2022.112060
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Nuclear reactor thermal hydraulics (NTH) has been developed during the last six decades as an important discipline for nuclear reactor design, safety analysis and operational support. Many achievements have been made, but there remain areas to be further developed. This paper summarizes the papers presented in the Round Table session on Envisaged future for nuclear thermal-hydraulics, as part of the OECD/NEA/CSNI Specialists Meeting on Transient Thermal hydraulics in Water Cooled Nuclear Reactors (SM-TH). In addition, the per-spectives for future development in selected NTH topics are briefly discussed from the industrial application point of view, based on a review of these papers and the discussion at the meeting, as well as some recent publications.
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页数:8
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