Source terms analysis of a maximum release accident for an AGN-201M reactor
- Univ of New Mexico, Albuquerque (United States)
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.
- OSTI ID:
- 7073716
- Report Number(s):
- CONF-911107--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 63; ISSN TANSA; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ACTIVITY LEVELS
AEROJET-GENERAL NUCLEONICS REACTORS
AEROSOLS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CARBON
CHALCOGENIDES
COLLOIDS
CONTROL ELEMENTS
CONVECTION
DAYS LIVING RADIOISOTOPES
DEPOSITION
DEVELOPED COUNTRIES
DISPERSIONS
DOSES
ELEMENTAL MINERALS
ELEMENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
ENVIRONMENTAL EXPOSURE PATHWAY
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FEDERAL REGION VI
FISSION PRODUCT RELEASE
FOOD CHAINS
GRAPHITE
HALOGENS
HAZARDS
HEALTH HAZARDS
HEAT TRANSFER
HOMOGENEOUS REACTORS
HOURS LIVING RADIOISOTOPES
HYDROGEN COMPOUNDS
INGESTION
INHALATION
INTAKE
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
IODINE
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
KRYPTON 85
KRYPTON 87
KRYPTON 88
KRYPTON ISOTOPES
LEAD
MASS TRANSFER
METALS
MICROSEC LIVING RADIOISOTOPES
MINERALS
MINUTES LIVING RADIOISOTOPES
MODERATORS
NATURAL CONVECTION
NEUTRON REFLECTORS
NEW MEXICO
NONMETALS
NORTH AMERICA
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PUBLIC HEALTH
RADIATION DOSES
RADIATION HAZARDS
RADIOACTIVE AEROSOLS
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
RISK ASSESSMENT
SCRAM RODS
SOLID HOMOGENEOUS REACTORS
SOLS
SOURCE TERMS
THERMAL REACTORS
TRAINING REACTORS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
USA
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WATER
XENON 133
XENON 135
XENON 138
XENON ISOTOPES
YEARS LIVING RADIOISOTOPES