PRELIMINARY SAFETY ANALYSIS REPORT FOR THE LITHIUM COOLED REACTOR EXPERIMENT (LCRE)
Technical Report
·
OSTI ID:4675518
Modifications to the reactor test facility are described, and a maximum accident in which pipes break permitting coolant loss with resultant core meltdown is analyzed. A burst-cnergy release of 1.5 x 10/sup 6/ Btu is considered. A pressure-temperature time history is calculated, taking into account fission product decay heat, chemical reaction heat, and sensible heat of experiment components. The dose rate at the outer surface of the cell was estimated to be 2.2 r/hr immediately after, and 17 mr/hr 17 min after, the excursion. The highest offsite dose from fission product release is estimated to be about 6 rem. The results indicate that even a maximum accident in the facility would result in an acceptably small risk to the public. (D.C.W.)
- Research Organization:
- Pratt and Whitney Aircraft Div., United Aircraft Corp. Connecticut Aircraft Nuclear Engine Lab., Middletown
- DOE Contract Number:
- AT(30-1)-2789
- NSA Number:
- NSA-17-031732
- OSTI ID:
- 4675518
- Report Number(s):
- PWAC-370(Suppl.1)
- Country of Publication:
- United States
- Language:
- English
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