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Simulation of the response of the Fort St. Vrain high temperature gas cooled reactor system to a postulated rod withdrawal accident

Conference ·
OSTI ID:5450867
; ; ; ;

Transients resulting from the accidental withdrawal of a control rod pair from the Fort St. Vrain reactor core from 100% power conditions have been analyzed with the ORTAP nuclear steam supply system simulation. This analysis was done as part of an ongoing effort to obtain an independent assessment of the HTGR system response to several postulated accidents. Results are presented and discussed.

Research Organization:
Oak Ridge National Lab., Tenn. (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5450867
Report Number(s):
CONF-770708-1
Country of Publication:
United States
Language:
English

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REACTIVITY INSERTIONS
REACTOR ACCIDENTS
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