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Assessment of the RELAP4/MOD6 reactor transient thermal-hydraulic code

Conference ·
OSTI ID:5908867
; ;
The RELAP4/MOD6 transient analysis code is the most recently released of a set of computer programs designed for calculation of the thermal-hydraulic behavior of a light water reactor (LWR) during the transient phases of a postulated loss-of-coolant accident. Earlier versions of RELAP4 primarily had capability for analysis of blowdown and refill phenomena. With RELAP4/MOD6, this capability has been extended through the core reflood range, uniquely providing a best estimate analysis code for the entire accident period. The code has been assessed by comparing and evaluating calculations with results of a broad selection of reactor safety experiments. This assessment represents a new procedure that incorporates the results of code-data comparisons and evaluations made under controlled user-oriented conditions and introduces a conventional statistical approach to the analysis of code prediction uncertainties. The assessement procedure quantifies the uncertainties in the code in application to the modeling of experiments varying in size, scale, and scope.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
5908867
Report Number(s):
CONF-791103-4(Summ)
Country of Publication:
United States
Language:
English

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