Published 1991 | Version v1
Journal article

Source terms analysis of a maximum release accident for an AGN-201M reactor

  • 1. Univ of New Mexico, Albuquerque (United States)

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--.