HTGR accident initiation and progression analysis status report. Volume V. AIPA fission product source terms
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.
- Research Organization:
- General Atomic Co., San Diego, Calif. (USA)
- DOE Contract Number:
- E(04-3)-167
- OSTI ID:
- 7283899
- Report Number(s):
- GA-A-13617(Vol.5)
- Country of Publication:
- United States
- Language:
- English
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