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BWR lower plenum debris bed models for MELCOR [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Oak Ridge National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Las Vegas. Nev. : Oak Ridge, Tenn. : U.S. Department of Energy Yucca Mountain Site Characterization Project ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1991.
Subjects:	Water Moderated Reactors. Blackouts. Computerized Simulation. Water Cooled Reactors. Bwr Type Reactors. Reactors. Enriched Uranium Reactors. Simulation. M Codes. Power Reactors. Reactor Cores. Reactor Internals. B Codes. Corium. Reactor Components. Computer Codes. Accidents. Fuel Assemblies. Thermal Reactors. Reactor Accidents. General Studies Of Nuclear Reactors.

Description
Abstract:	Work is underway at Oak Ridge National Laboratory (ORNL) to incorporate certain models of the Boiling Water Reactor Severe Accident Response (BWRSAR) code into a local version of MELCOR. Specifically, the BWR lower plenum debris bed and bottom head response models taken from BWRSAR are being tested within the local MELCOR code structure. Upon successful completion of testing, recommendations for formal adoption of these models will be made to the Nuclear Regulatory Commission (NRC) and to the MELCOR code development staff at Sandia National Laboratories (SNL). The SNL code development staff retain exclusive responsibility for maintaining the configuration control for the official version of MELCOR. The BWR lower plenum debris bed and bottom head response models permit the calculation of heatup, melting, and relocation of the debris after dryout. They predict the response of the lower plenum internal structures and the bottom head as well as the composition and timing of material release from the vessel. They have been previously applied in severe accident analyses for the Containment Performance Improvement (CPI) Program and the Mark I shell survivability study (NUREG/CR-5423), and in recent assessments of candidate accident management strategies. This paper provides a brief description of the purpose and operation of these models. 11 refs., 15 figs., 5 tabs.
Item Description:	Published through the Information Bridge: DOE Scientific and Technical Information. 01/01/1991. "conf-911079-1" "DE92001975" 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting, Bethesda, MD (United States), 28-30 Oct 1991. Hodge, S.A.; Ott, L.J.
Physical Description:	Pages: (25 p) : digital, PDF file.