Radiological consequence analyses under severe accident conditions for the advanced neutron source reactor at the Oak Ridge National Laboratory
Journal Article
·
· Nuclear Safety; (United States)
OSTI ID:7246633
- Oak Ridge National Lab., TN (United States)
This article discusses salient aspects of methodology, assumptions, and modeling of various features related to radiation exposure and the health consequences from source terms resulting from two conservatively scoped severe accident scenarios. Radiological consequences for a site-suitability scenario based on 10 CFR 100 guidelines also are presented. Consequences arising from severe accidents involving steaming pools and core-concrete interaction (CCI) events combined with several different containment configurations are presented. Results are presented in the form of mean cumulative values for prompt and latent cancer fatality estimates and related cumulative, complementary distribution functions as a function of distance from the reactor site. It is shown that the reactor site-suitability risk goals are met by a large margin and that overall risk is dominated by early containment failure combined with CCI events. 9 refs., 1 fig., 5 tabs.
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7246633
- Journal Information:
- Nuclear Safety; (United States), Journal Name: Nuclear Safety; (United States) Vol. 34:2; ISSN 0029-5604; ISSN NUSAAZ
- Country of Publication:
- United States
- Language:
- English
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Radiological consequence analyses under severe accident conditions for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory
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Conference
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Thu Oct 01 00:00:00 EDT 1992
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Radiological consequence analyses under severe accident conditions for the Advanced Neutron Source Reactor at the Oak Ridge National Laboratory
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
560180 -- Radiation Protection Procedures-- (1992-)
61 RADIATION PROTECTION AND DOSIMETRY
ACCIDENTS
CONTAINMENT
CONTAINMENT SYSTEMS
DATA
DISEASES
DOSES
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
INFORMATION
ISOTOPES
NEOPLASMS
NUMERICAL DATA
PLUMES
RADIATION DOSES
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RISK ASSESSMENT
SAFETY
THEORETICAL DATA
22 GENERAL STUDIES OF NUCLEAR REACTORS
220504 -- Nuclear Reactor Technology-- Environmental Aspects-- Design Basis & Hypothetical Accidents-- (1992-)
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
560180 -- Radiation Protection Procedures-- (1992-)
61 RADIATION PROTECTION AND DOSIMETRY
ACCIDENTS
CONTAINMENT
CONTAINMENT SYSTEMS
DATA
DISEASES
DOSES
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
INFORMATION
ISOTOPES
NEOPLASMS
NUMERICAL DATA
PLUMES
RADIATION DOSES
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RISK ASSESSMENT
SAFETY
THEORETICAL DATA