skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: PUMA test program for SBWR

Conference ·
OSTI ID:269714
; ;  [1]
  1. Purdue Univ., West Lafayette, IN (United States); and others

The objective of the PUMA integral test program is to obtain confirmatory test data for the SBWR Developed by the General Electric-Nuclear Energy Company. The program was initiated in July 1993 under the sponsorship of the NRC. The SBWR has a simplified coolant circulation system and a passive emergency cooling system. The engineered safety systems and safety-grade systems in the SBWR are: (1) the Automatic Depressurization System (ADS), (2) the Gravity-Driven Cooling System (GDCS), (3) the Passive Containment Cooling System (PCCS), (4) the Isolation Condenser Systems (ICS), and (5) the Pressure Suppression Pool (SP). The GDCS and PCCS are new designs unique to the SBWR and do not exist in operating BWRs. The ICS is similar to those in some operating BWRs. The PCCS is designed for low-pressure operation for the containment cooling, but the ICS is capable of high pressure operation as well to cool the reactor pressure vessel. The PUMA design was completed based on an extensive scaling analysis. The PUMA facility having 1/4 height and 1/400 volume scales is constructed. Various facility characterization tests and instrumentation and data acquisition system checks are performed presently. The facility acceptance test will be performed in November and integral tests will be initiated.

Research Organization:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab. (BNL), Upton, NY (United States)
OSTI ID:
269714
Report Number(s):
NUREG/CP-0149-Vol.1; CONF-9510156-Vol.1; ON: TI96009154; TRN: 96:016820
Resource Relation:
Conference: 23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995; Other Information: PBD: Mar 1996; Related Information: Is Part Of Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 265 p.
Country of Publication:
United States
Language:
English