HTGR accident initiation and progression analysis status report. Volume V. AIPA fission product source terms
Description
The primary objective of the Accident Initiation and Progression Analysis (AIPA) Program is to provide guidance for high-temperature gas-cooled reactor (HTGR) safety research and development. Among the parameters considered in estimating the uncertainties in site boundary doses are uncertainties in fission product source terms generated under normal operating conditions, i.e., fuel body inventories, circulating coolant activity, total plateout activity in the primary circuit, and plateout distributions. The volume presented documents the analyses of these source term uncertainties. The results are used for the detailed consequence evaluations, and they provide the basis for evaluation of fission products important for HTGR maintenance and shielding
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS.
Files
Restricted
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Additional details
Publishing Information
- Imprint Pagination
- 296 p.
- Report number
- GA-A--13617(Vol.5)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7268658
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FISSION PRODUCT RELEASE; FISSION PRODUCTS; HTGR TYPE REACTORS; MATHEMATICAL MODELS; RADIATION DOSES; REACTOR ACCIDENTS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; ISOTOPES; RADIOACTIVE MATERIALS; REACTORS; SAFETY
Optional Information
- Notes
- Available from NTIS. $7.60.