Nuclear reactor safety. Quarterly progress report, July 1--September 30, 1978. [BWR; PWR; HTGR; LMFBR; GCFR]

Technical Report · Wed Nov 01 04:00:00 EST 1978

OSTI ID:6494212

Jackson, J F; Stevenson, M G ^[1]

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1. comps.

Development of the TRAC LWR safety code continued during the last quarter, with the final program structure changes being completed for the TRAC-P1A version. Other TRAC applications included a sensitivity study to examine some of the effects of downcomer dynamics on calculated peak clad temperatures during a LOCA in a typical PWR. Also, a new computational method for treating droplet fields with a distribution of drop sizes was developed. LMFBR safety studies included completion of a SIMMER-II sensitivity study of a voided core postdisassembly expansion problem. SIMMER-II was also used to analyze TREAT loss-of-flow test R-7. SIMMER verification analyses also included calculations of SRI International bubble expansion experiments. A detailed scaling and preliminary feasibility study of a postdisassembly upper core structure simulation experiment was completed. In LMFBR safety test facilities work, hodoscope scanning of a 127-pin bundle in the PARKA critical facility was continued. Structural investigations in the HTGR safety research area included completion of single impact tests of graphite and plastic model blocks. A major milestone was reached in completing all component modules for the CHAP-2 (Ft. St. Vrian) HTGR systems analysis program. CHAP-2 studies were made of depressurization accidents with air and steam ingress to the primary system and of feedwater transients. In the GCFR core distruptive test program, postmortem examinations of the FLS-1 37-pin disruptive test indicated considerable molten cladding flow occurred in the experiment. Investigations were made into the cause of heater rod failure in this experiment. Containment systems evaluation work included studies of the effects of blockages of reactor cavity flow areas assumed to be caused by pieces of insulation loosened during a LOCA. The MOD-2 version of the COMPARE code was prepared for release to the National Energy Software Center (formerly the Argonne Code Center).

• Research Organization: Los Alamos Scientific Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6494212
• Report Number(s): NUREG/CR-0522; LA-7567-PR
• Country of Publication: United States
• Language: English

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