An overview of severe accident modeling and analysis work for the ANS reactor conceptual safety analysis report

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:7086767

Taleyarkhan, R P

ORNL's Advanced Neutron Source (ANS) will be a new user facility for all kinds of neutron research, centered around a research reactor of unprecedented neutron beam flux. A defense-in-depth philosophy has been adopted. In response to this commitment, ANS Project management has initiated severe accident analysis and related technology development efforts early-on in the design phase itself. Early consideration of severe accident issues will aid in designing a sufficiently robust containment for retention and controlled release of radionuclides in the event of such an accident. It will also provide a means for satisfying on- and off-site regulatory requirements and provide containment response and source term analyses for level-2 and -3 Probabilistic Risk Analyses (PRAs) that will be produced. Moreover, it will provide the best possible understanding of the ANS under severe accident conditions, and consequently provide insights for the development of strategies and design philosophies for accident management, mitigation, and emergency preparedness. This paper presents a perspective overview of the severe accident modeling and analysis work for the ANS Conceptual Safety Analysis Report (CSAR)

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 7086767
• Report Number(s): CONF-9211119-1; ON: DE93003094
• Resource Relation: Conference: 3. nuclear reactor severe accident workshop, Tokyo (Japan), 4-6 Nov 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
ORNL
RESEARCH REACTORS
REACTOR ACCIDENTS
MANAGEMENT
SAFETY ANALYSIS
AEROSOLS
CONTAINMENT
CORIUM
FISSION PRODUCT RELEASE
M CODES
NEOPLASMS
PUBLIC HEALTH
RADIATION DOSES
RADIATION TRANSPORT
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
COLLOIDS
COMPUTER CODES
DISEASES
DISPERSIONS
DOSES
NATIONAL ORGANIZATIONS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
990200 - Mathematics & Computers