CONTAINMENT OF A LARGE SODIUM-COOLED FAST BREEDER REACTOR
Technical Report
·
OSTI ID:4362332
A practicable model for analysis of containment leakages, after excursion, is proposed for Na-cooled fast breeder reactors. A conceptual design study of a 300 MW(e) prototype is made to illustrate that use of double-containment precludes environmental hazard. (M.L.S.)
- Research Organization:
- Kernforschungszentrum, Karlsruhe (West Germany)
- NSA Number:
- NSA-21-030137
- OSTI ID:
- 4362332
- Report Number(s):
- EURFNR--289; KFK--547
- Country of Publication:
- Germany
- Language:
- English
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