Radionuclide release calculations for selected severe accident scenarios

Technical Report · Wed Aug 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6604655· OSTI ID:6604655

Denning, R S; Leonard, M T; Cybulskis, P; Lee, K W; Kelly, R F; Jordan, H; Schumacher, P M; Curtis, L A ^[1]

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1. Battelle Columbus Div., OH (USA)

This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Battelle Columbus Div., OH (USA)
• Sponsoring Organization: USNRC
• OSTI ID: 6604655
• Report Number(s): NUREG/CR-4624-Vol.6; BMI-2139-Vol.6; ON: TI90017696; TRN: 90-029484
• Country of Publication: United States
• Language: English

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SEQUOYAH-1 REACTOR
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