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Title: Preliminary risks associated with postulated tritium release from production reactor operation

Conference ·
OSTI ID:5074917

The Probabilistic Risk Assessment (PRA) of Savannah River Plant (SRP) reactor operation is assessing the off-site risk due to tritium releases during postulated full or partial loss of heavy water moderator accidents. Other sources of tritium in the reactor are less likely to contribute to off-site risk in non-fuel melting accident scenarios. Preliminary determination of the frequency of average partial moderator loss (including incidents with leaks as small as .5 kg) yields an estimate of /approximately/1 per reactor year. The full moderator loss frequency is conservatively chosen as 5 /times/ 10/sup /minus/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 4 /times/ 10/sup /minus/8/ per reactor year within 16 km of the release point. The full moderator loss accident contributes about 75% of the evaluated risks. 13 refs., 4 figs., 5 tabs.

Research Organization:
Savannah River Lab., Aiken, SC (USA)
DOE Contract Number:
AC09-76SR00001
OSTI ID:
5074917
Report Number(s):
DP-MS-87-143; CONF-880505-15; ON: DE88009307
Resource Relation:
Conference: 3. topical meeting on tritium technology in fission, fusion and isotopic applications, Toronto, Canada, 1 May 1988
Country of Publication:
United States
Language:
English