Ex-vessel fission product release modeling
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5538049
Release of fission products from core debris after reactor vessel failure is of interest in current severe accident source term research. This paper focuses on significant physical phenomena, requirements, and feedbacks in the context of integrated accident analysis for modeling these releases after initial corium distribution outside the vessel. There are many assumptions made in integrated accident analyses to which ex-vessel fission product release is sensitive. One assumption internal to the release model, the allowed species list, has been demonstrated to significantly affect release of strontium and lanthanum.
- Research Organization:
- Fauske and Associates, Willow Brook, IL
- OSTI ID:
- 5538049
- Report Number(s):
- CONF-851115-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
COMPUTER CODES
CONCRETES
CONTAINERS
CORIUM
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL ELEMENT FAILURE
ISOTOPES
M CODES
MATERIALS
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
PRESSURE VESSELS
RADIOACTIVE MATERIALS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
RESEARCH PROGRAMS
SAFETY
SANDIA LABORATORIES
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
V CODES
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
COMPUTER CODES
CONCRETES
CONTAINERS
CORIUM
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL ELEMENT FAILURE
ISOTOPES
M CODES
MATERIALS
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
PRESSURE VESSELS
RADIOACTIVE MATERIALS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
RESEARCH PROGRAMS
SAFETY
SANDIA LABORATORIES
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
V CODES