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- W1602078713 abstract "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 5×10−3 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 2×10−8 per reactor-year within 16 km of the release point. The full moderator loss accident contributes about 80% of the evaluated risks." @default.
- W1602078713 created "2016-06-24" @default.
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- W1602078713 date "1988-09-01" @default.
- W1602078713 modified "2023-09-23" @default.
- W1602078713 title "Preliminary Risks Associated with Postulated Tritium Release from Production Reactor Operation" @default.
- W1602078713 cites W2074856814 @default.
- W1602078713 doi "https://doi.org/10.13182/fst88-a25290" @default.
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