Pretest mediction of Semiscale Test S-07-10 B. [PWR]

Technical Report · Fri Jun 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/6142379· OSTI ID:6142379

Dobbe, C A

A best estimate prediction of Semiscale Test S-07-10B was performed at INEL by EG and G Idaho as part of the RELAP4/MOD6 code assessment effort and as the Nuclear Regulatory Commission pretest calculation for the Small Break Experiment. The RELAP4/MOD6 Update 4 and the RELAP4/MOD7 computer codes were used to analyze Semiscale Test S-07-10B, a 10% communicative cold leg break experiment. The Semiscale Mod-3 system utilized an electrially heated simulated core operating at a power level of 1.94 MW. The initial system pressure and temperature in the upper plenum was 2276 psia and 604/sup 0/F, respectively.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6142379
• Report Number(s): CAAP-TR-052
• Country of Publication: United States
• Language: English

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