Effect of primary pump coastdown on unprotected loss-of-flow transients in EBR-II
A loss-of-flow (LOF) accident of considerable interest in current LMFBR safety study is a total loss of pumping power coupled with a failure of the reactor shutdown system (RSS). Confirming predictions of this type of unprotected transient is the primary purpose of the Shutdown Heat Removal Tests (SHRT) presently scheduled for June 1985 in the Experimental Breeder Reactor II (EBR-II). The tests are also intended to validate predictions of the maximum operating power at which the reactor can safely sustain a total loss of power (station blackout) and a failure of RSS. An extensive series of tests was successfully completed in June of 1984 which investigated the reactor shutdown cooling capability following protected LOF events and the inherent reactivity feedback characteristics in EBR-II in preparation for making predictions of the upcoming unprotected tests. This paper discusses details of the unprotected LOF transient analysis, the validation of the EBR-II reactivity feedback modeling, and the significance of primary pump coastdown characteristics on peak reactor temperature.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5986422
- Report Number(s):
- CONF-850420-2; ON: DE85002148; TRN: 85-007445
- Resource Relation:
- Conference: 2. specialists' meeting on decay heat removal and natural convection in LMFBRs, Long Island, NY, USA, 17 Apr 1985
- Country of Publication:
- United States
- Language:
- English
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