For the thermal hydraulic and safety analysis of nuclear reactor, a lot of theoretical models and engineering experience are mainly contained in the design software. The degree of self-reliance of software directly reflects the technological level and core competencies. According to the nuclear power plant (NPP) design requirements, self-reliant thermal hydraulic and safety analysis software, such as CORTH, TRANTH, PHYCA and etc., have been developed by Nuclear Power Institute of China (NPIC) with reasonable planning and scientific implementation. In this paper, the development process of the self-reliant software is reviewed, covering requirement analysis, model research, software design, coding, testing, verification and validation. And the main characteristics of self-reliant software were summarized. The successful development of thermal hydraulic and safety analysis software support the export of nuclear power units of China, and enhance the competitiveness.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5149-4
PROCEEDINGS PAPER
Development of Self-Reliant Thermal Hydraulic and Safety Analysis Software for NPP Design Available to Purchase
Yu Liu,
Yu Liu
Nuclear Power Institute of China, Chengdu, China
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Jian Deng,
Jian Deng
Nuclear Power Institute of China, Chengdu, China
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Junjie Pan,
Junjie Pan
Nuclear Power Institute of China, Chengdu, China
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Zongjian Lu
Zongjian Lu
Nuclear Power Institute of China, Chengdu, China
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Yu Liu
Nuclear Power Institute of China, Chengdu, China
Jian Deng
Nuclear Power Institute of China, Chengdu, China
Junjie Pan
Nuclear Power Institute of China, Chengdu, China
Zongjian Lu
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE26-82031, V06BT08A021; 7 pages
Published Online:
October 24, 2018
Citation
Liu, Y, Deng, J, Pan, J, & Lu, Z. "Development of Self-Reliant Thermal Hydraulic and Safety Analysis Software for NPP Design." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06BT08A021. ASME. https://doi.org/10.1115/ICONE26-82031
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