Scaling and design of PUMA and SBWR

Conference · Sat Oct 01 00:00:00 EDT 1994

OSTI ID:54606

Ishii, M; Revankar, S T; Dowlati, R; Bertodano, M L; Babelli, I; Wang, W; Pokharna, H; Ransom, V H; Viskanta, R

The General Electric Nuclear Energy (GE) has developed a new boiling water reactor called the Simplified Boiling Water Reactor (SBWR). Major differences between the current Boiling Water Reactors (BWRs) and the SBWR are in the simplification of the coolant circulation system and the implementation of passive emergency cooling systems. There are no recirculation pumps to drive the coolant in the vessel of the SBWR. The emergency core cooling and containment cooling systems do not have active pump-injected flows.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research
• OSTI ID: 54606
• Report Number(s): NUREG/CP-0139; CONF-9410216-; ON: TI95001469; TRN: 95:012640
• Resource Relation: Conference: 22. water reactor safety information meeting, Bethesda, MD (United States), 24-26 Oct 1994; Other Information: PBD: Oct 1994; Related Information: Is Part Of Transactions of the twenty-second water reactor safety information meeting; PB: 129 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
22 NUCLEAR REACTOR TECHNOLOGY
BWR TYPE REACTORS
TECHNOLOGY ASSESSMENT
DESIGN
REACTOR COMPONENTS
NUCLEAR POWER PLANTS
REACTOR SAFETY