Passive containment cooling system performance in the simplified boiling water reactor
- GE Nuclear Energy, San Jose, CA (United States)
- ETH/PSI, Zurich (Switzerland)
The Simplified Boiling Water Reactor (SBWR) incorporates a passive system for decay heat removal from the containment in the event of a postulated Loss-of-Coolant Accident (LOCA). Decay heat is removed by condensation of the steam discharged from the reactor pressure vessel (RPV) in three condensers which comprise the Passive Containment Cooling System (PCCS). These condensers are designed to carry the heat load while transporting a mixture of steam and noncondensible gas (primarily nitrogen) from the drywell to the suppression chamber. This paper describes the expected LOCA response of the SBWR with respect to the PCCS performance, based on analysis and test results. The results confirm that the PCCS has excess capacity for decay heat removal and that overall system performance is very robust. 12 refs., 8 figs.
- OSTI ID:
- 549118
- Report Number(s):
- CONF-970607-Vol.1; TRN: 98:000393
- Resource Relation:
- Conference: ARS `97: American Nuclear Society (ANS) international meeting on advanced reactors safety, Orlando, FL (United States), 1-5 Jun 1997; Other Information: PBD: 1997; Related Information: Is Part Of Proceedings of the international topical meeting on advanced reactors safety: Volume 1; PB: 640 p.
- Country of Publication:
- United States
- Language:
- English
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