Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor
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Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor
Thermal Power GenerationVol. 45, Issue 12, Pages: 67-72(2016)
作者机构:
国核电力规划设计研究院
作者简介:
基金信息:
DOI:
CLC:TM623
Published:2016
稿件说明:
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ZHU Xinwei, ZHANG Guiying, SHAO Jie, et al. Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor[J]. Thermal power generation, 2016, 45(12): 67-72.
DOI:
ZHU Xinwei, ZHANG Guiying, SHAO Jie, et al. Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor[J]. Thermal power generation, 2016, 45(12): 67-72.DOI:
Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor
Hazard analysis for high energy piping double ended break is the key content of nuclear power plants conventional island design.On the basis of summarizing the hazard analysis of conventional pipe rupture in nuclear power plants
the paper puts forward a set of methods for main steam pipe rupture hazard analysis for high temperature gas-cooled reactor
according to the characteristics of high temperature gascooled reactor.It suggests that the stress analysis method be adopted for break point selection
the simplified algorithm and thermal-hydraulics algorithm be employed for spray force calculation
and the method given in the ANSI/ANS—58.2—1988be used to compute the jet shape under two conditions
the unstinted rupture and confined finite separation rupture.The pipeline's dynamic response analysis can be realized using the finite simulation algorithm
and the over-pressure watered out effect after the double ended break occurred on the steam pipeline of the high temperature gas-cooled reaction should be analyzed according to the specific engineering arrangement of the pipelines.This analysis method provides the basis for design of main steam pipe whip restraints for high temperature gas-cooled reactor nuclear power plants.