MELCOR-calculated in-containment source terms using different release models
- Lockheed Martin Energy Research, Oak Ridge, TN (United States)
This study compares in-containment source terms calculated with the severe-accident code MELCOR, version 1.8.3 (1.8PZ), using six different release models for fission products. The source terms were calculated for a low-pressure, short-term station blackout severe accident at the Grand Gulf nuclear station. The Grand Gulf nuclear station, unit 1, is a General Electric boiling water reactor (BWR)-6 with a Mark-III containment located in Port Gibson, Mississippi. The reactor`s full power is 3833 MW(thermal) with a net electrical output of 1250 MW(electric). The steamlines of the reactor vessel are connected to 20 safety relief valves (SRVs). The automatic depressurization system (ADS) simultaneously opens eight of these SRVs. The severe accident simulated is a station blackout with all power lost, except the batteries needed to operate the SRVs and the ADS. Manual operation of the ADS is used to depressurize the reactor in conformance with Ref. 3 of the BWR Owners Group Emergency Procedures Guidelines (EPGs). Revision 3 of the EPGs requires manual actuation of the ADS when the water level in the core is at about one-third of the core active height (equivalent to two-thirds of the core uncovered).
- OSTI ID:
- 436957
- Report Number(s):
- CONF-9606116--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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