Source terms analysis of a maximum release accident for an AGN-201M reactor
Description
The fundamental liability of any nuclear reactor is the possibility of exposing the public and environment to an excessive level of nuclear radiation. In a previous paper, the authors addressed the risk and potential vulnerability assessment of a maximum hypothetical release accident (MHRA) for the AGN-201M reactor at the University of New Mexico. The MHRA is defined as the total release of all radiological effluents from the reactor facility to the environment. A level I probabilistic risk assessment was performed to assess the risk to the public. The type of effluents, total activity, maximum exposure rate, and related health effects associated with an MHRA were analyzed in an attempt to identify the source term and its consequences. The source term was characterized for the worst-case scenario only because the magnitude of the released effluents is deemed ineffectual for any subcategory release
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Journal Page Range
- p. 411.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24016030
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTIVITY LEVELS; AEROJET-GENERAL NUCLEONICS R; CONTROL ELEMENTS; DEPOSITION; ENVIRONMENTAL EXPOSURE PATHWAY; FISSION PRODUCT RELEASE; FOOD CHAINS; GRAPHITE; INGESTION; INHALATION; IODINE; KRYPTON 85; KRYPTON 87; KRYPTON 88; LEAD; MODERATORS; NATURAL CONVECTION; NEUTRON REFLECTORS; NEW MEXICO; PUBLIC HEALTH; RADIATION DOSES; RADIATION HAZARDS; RADIOACTIVE AEROSOLS; REACTOR ACCIDENTS; REACTOR CORES; RISK ASSESSMENT; SCRAM RODS; SOURCE TERMS; URANIUM DIOXIDE; VENTILATION SYSTEMS; WATER; XENON 133; XENON 135; XENON 138
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; AEROSOLS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON; CHALCOGENIDES; COLLOIDS; CONVECTION; DAYS LIVING RADIOISOTOPES; DEVELOPED COUNTRIES; DISPERSIONS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; HALOGENS; HAZARDS; HEALTH HAZARDS; HEAT TRANSFER; HOMOGENEOUS REACTORS; HOURS LIVING RADIOISOTOPES; HYDROGEN COMPOUNDS; INTAKE; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KRYPTON ISOTOPES; MEDICINE; METALS; MICROSEC LIVING RADIOISOTOPES; MINUTES LIVING RADIOISOTOPES; NONMETALS; NORTH AMERICA; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PREVENTIVE MEDICINE; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; SOLS; THERMAL REACTORS; TRAINING REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; USA; XENON ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-911107--.