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Harrington, R.M.; Ball, S.J.; Kornegay, F.C.
Oak Ridge National Lab., TN (USA)1982
Oak Ridge National Lab., TN (USA)1982
AbstractAbstract
[en] Thermal-hydraulic, fission product transport, and atmospheric dispersion calculations are presented for hypothetical severe accident release paths at the Fort St. Vrain (FSV) high temperature gas cooled reactor (HTGR). Off-site radiation exposures are calculated for assumed release of 100% of the 24 hour post-shutdown core xenon and krypton inventory and 5.5% of the iodine inventory. The results show conditions under which dose avoidance measures would be desirable and demonstrate the importance of specific release characteristics such as effective release height. 7 tables
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1982; 17 p; 3. Japan/US HTGR safety technology seminar; Upton, NY (USA); 2 - 3 Jun 1982; Available from NTIS., PC A02/MF A01 as DE82017318
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Report
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Conference
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