Heat removal aspects of Liquid Metal Fast Breeder Reactor safety in light of the Three Mile Island incident
The safety aspects of the Liquid Metal Fast Breeder Reactor (LMFBR) loop design are compared with those of the Light Water Reactor (LWR), in light of the Three Mile Island (TMI) incident. The events at TMI are briefly described, the fundamental differences between the LWR water coolant and the LMFBR sodium coolant are presented, and the design of analogous LMFBR safety systems under similar events as those at TMI is discussed. A preliminary qualitative evaluation of a TMI-equivalent accident for an LMFBR indicates that there is likely to be: (1) negligible pressure transients in the primary loop, (2) no core damage, (3) isolation of the incident at the steam generator, and (4) no radiation release to the environment, except a negligible amount of tritium from the secondary sodium. Furthermore, with the absence of the ECCS (Emergency Core Cooling System), pressurizer, and other pressure-related components in the LMFBR design, operator action for a LMFBR should be much simpler in dealing with the coolant upset condition and the decay heat removal problems.
- Research Organization:
- Breeder Reactor Division, Burns and Roe, Inc., Oradell, New Jersey
- OSTI ID:
- 6883836
- Report Number(s):
- CONF-801210-
- Journal Information:
- Alternative Energy Sources; (United States), Journal Name: Alternative Energy Sources; (United States) Vol. 5; ISSN ALESD
- Country of Publication:
- United States
- Language:
- English
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