Small break LOCA (loss of coolant accident) mitigation for Bellefonte
Several 5-cm (2-in.) diameter cold leg break loss coolant accidents for the Bellefonte nuclear plant were analyzed as part of the Severe Accident Sequence Analysis Program. The transients assumed various system failures, and included the S/sub 2/D sequence. Operator actions to mitigate the S/sub 2/D transient were also investigated. The transients were analyzed until either core damage began or long-term decay heat removal was established. The S/sub 2/D sequence was analyzed into the core damage phase of the transient. The analyses showed that the flow from one high pressure injection pump was necessary and sufficient to prevent core damage in the absence of operator actions. Operator actions were also able to prevent core damage for the S/sub 2/D sequence.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 7037686
- Report Number(s):
- EGG-M-22286; CONF-8610135-23; ON: DE87002613
- Resource Relation:
- Conference: 14. water reactor safety information meeting, Gaithersburg, MD, USA, 27 Oct 1986; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BELLEFONTE-1 REACTOR
LOSS OF COOLANT
BELLEFONTE-2 REACTOR
HEAT TRANSFER
HYDRAULICS
MITIGATION
ACCIDENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled