Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor

Autor:	Guo Yun, Liu Tiancai, Zhang Jianwei, Qiu Suizheng, Jia Dounan, Tian Wenxi, Su Guanghui
Rok vydání:	2007
Předmět:	Engineering business.industry Nuclear engineering Mass flow Flow (psychology) Energy Engineering and Power Technology Mechanical engineering Power (physics) Stress (mechanics) Thermal hydraulics Nuclear reactor core Research reactor business Communication channel
Zdroj:	Frontiers of Energy and Power Engineering in China. 1:189-194
ISSN:	1673-7504 1673-7393
DOI:	10.1007/s00000-007-0024-8
Popis:	A multi-channel model steady-state thermal-hydraulic analysis code was developed for the China Advanced Research Reactor (CARR). By simulating the whole reactor core, the detailed mass flow distribution in the core was obtained. The result shows that structure size plays the most important role in mass flow distribution, and the influence of core power could be neglected under single-phase flow. The temperature field of the fuel element under unsymmetrical cooling condition was also obtained, which is necessary for further study such as stress analysis, etc. of the fuel element. At the same time, considering the hot channel effect including engineering factor and nuclear factor, calculation of the mean and hot channel was carried out and it is proved that all thermal-hydraulic parameters satisfy the “Safety design regulation of CARR”.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::34a0297b0d29c7dc83cfd3093389ad5a https://doi.org/10.1007/s00000-007-0024-8 Zobrazit plný text záznamu Full text from SpringerLink