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- W295093457 abstract "The purpose of this paper is to determine the impact of the core meltdown model parameters on in-vessel hydrogen generation and radiological release for an anticipated transient without scram scenario in a boiling water reactor. As part of a continuing effort to quantify the radiological source term from a severe accident in a light water reactor, the US Nuclear Regulatory Commission (NRC) sponsored the development of the Source Term Code Package (STCP). In order to better establish the validity and potential applications of source term predictions from these codes, the Quantification and Uncertainty Analysis of Source Term for Severe Accidents in Light Water Reactors (QUASAR) program was initiated at Brookhaven National Lab. under the sponsorship of the NRC to quantify the uncertainties associated with the STCP calculated source term. The core melt progression model in the STCP is included in the MARCH code. The results of the sensitivity studies summarized. The in-vessel hydrogen generation and fission product release predictions are strongly influenced by the assumptions related to the core melt progression. Large uncertainties exist over a wide range of parametrics as shown in this paper." @default.
- W295093457 created "2016-06-24" @default.
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- W295093457 date "1987-01-01" @default.
- W295093457 modified "2023-09-24" @default.
- W295093457 title "Sensitivity of in-vessel hydrogen generation and fission product release to parameter variations in a melt progression model" @default.
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