Published 1982
| Version v1
Report
Restricted
HTGR severe accident sequence analysis
Description
Thermal-hydraulic, fission product transport, and atmospheric dispersion calculations are presented for hypothetical severe accident release paths at the Fort St. Vrain high temperature gas cooled reactor. Off-site radiation exposures are calculated for assumed releases of 100% of the 24 hour post-shutdown core xenon and krypton inventory and 5.5% of the iodine inventory. The results show conditions under which dose avoidance measures would be desirable and demonstrate the importance of specific release characteristics such as effective release height
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Additional details
Publishing Information
- Imprint Title
- Third Japan-US seminar on HTGR safety technology: proceedings. Volume I
- Journal Page Range
- p. 158-172.
- Report number
- NUREG/CP--0045-Vol.1
Conference
- Title
- 3. Japan/US HTGR safety technology seminar.
- Dates
- 2-3 Jun 1982.
- Place
- Upton, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15033339
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CONTAINMENT SYSTEMS; DESIGN BASIS ACCIDENTS; FISSION PRODUCT RELEASE; HEAT TRANSFER; HTGR TYPE REACTORS; HYDRAULICS; IODINE; KRYPTON; LOSS OF COOLANT; PLUMES; PRIMARY COOLANT CIRCUITS; RADIATION HAZARDS; REACTOR VESSELS; STEAM GENERATORS; SYSTEMS ANALYSIS; VRAIN REACTOR; XENON
- Descriptors DEC
- ACCIDENTS; BOILERS; CONTAINERS; CONTAINMENT; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HALOGENS; HAZARDS; HEALTH HAZARDS; NONMETALS; POWER REACTORS; RARE GASES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; VAPOR GENERATORS