System code requirements for SBWR LOCA predictions
- Brookhaven National Lab., Upton, NY (United States)
The simplified boiling water reactor (SBWR) is the latest design in the family of boiling water reactors (BWRs) from General Electric. The concept is based on many innovative, passive, safety systems that rely on naturally occurring phenomena, such as natural circulation, gravity flows, and condensation. Reliability has been improved by eliminating active systems such as pumps and valves. The reactor pressure vessel (RPV) is connected to heat exchangers submerged in individual water tanks, which are open to atmosphere. These heat exchanger, or isolation condensers (ICs), provide a heat sink to reduce the RPV pressure when isolated. The RPV is also connected to three elevated tanks of water called the gravity-driven cooling system (GDCS). During a loss-of-coolant accident (LOCA), the RPV is depressurized by the automatic depressurization system (ADS), allowing the gravity-driven flow from the GDCS tanks. The containment pressure is controlled by a passive containment cooling system (PCCS) and suppression pool. Similarly, there are new plant protection systems in the SBWR, such as fine-motion control rod drive, passive standby liquid control system, and the automatic feedwater runback system. These safety and plant protection systems respond to phenomena that are different from previous BWR designs. System codes must be upgraded to include models for the phenomena expected during transients for the SBWR.
- OSTI ID:
- 89167
- Report Number(s):
- CONF-941102--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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