Preliminary risks associated with postulated tritium release from production reactor operation
Journal Article
·
· Fusion Technol.; (United States)
OSTI ID:6033809
The Probabilistic Risk Assessment (PRA) of Savannah River Plant (SRP) reactor operation is evaluating the offsite risk due to tritium releases during postulated full or partial loss of heavy water moderator accidents. Preliminary determination of the frequency of average partial moderator loss (including incidents with leaks as small as 0.5 kg) yields an estimate of --1 per reactor-year. The full moderator loss frequency is conservatively chosen as 5x10/sup -3/ per reactor-year. Conditional consequences, determined with a version of the MACCS code modified to handle tritium, are found to be insignificant. The 95th percentile individual cancer risk is 2x10/sup -8/ per reactor-year within 16 km of the release point. The full moderator loss accident contributes about 80% of the evaluated risks.
- Research Organization:
- Science Applications International Corp., Savannah River Lab., Aiken, SC (US); E.I. du Pont de Nemours and Co., Reactor Safety Research Div., Savannah River Lab., Aiken, SC (US)
- OSTI ID:
- 6033809
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 14:2; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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US AEC
US DOE
US ERDA
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WATER MODERATED REACTORS