Sensitivity of in-vessel hydrogen generation and fission product release to parameter variations in a melt progression model

Conference · Thu Jan 01 04:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5716652

Lee, M; Khatib-Rahbar, M

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.

• Research Organization: Brookhaven National Lab., Upton, NY
• OSTI ID: 5716652
• Report Number(s): CONF-870601-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 54
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BNL
BWR TYPE REACTORS
CHEMICAL REACTIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
CORIUM
ELEMENTS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HYDROGEN
M CODES
MELTDOWN
METALS
MOLTEN METAL-WATER REACTIONS
NATIONAL ORGANIZATIONS
NONMETALS
OXIDATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
SENSITIVITY ANALYSIS
SIMULATION
SOURCE TERMS
TRANSITION ELEMENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM