Loss-of-fluid test (LOFT) facility

Conference · Mon Jan 01 00:00:00 EST 1979

OSTI ID:6267439

Reeder, D L; Berta, V T

The Loss-of-Fluid Test (LOFT) facility is a 50 MW(t), volumetrically scaled, pressurized water reactor (PWR) system. The LOFT facility was designed to study the engineered safety features (ESF) in commercial PWR systems as to their response to the postulated loss-of-coolant accident (LOCA). With recognition of the differences in commercial PWR designs and inherent distortions in reduced scale systems, the design objective for the LOFT facility was to produce the significant thermal-hydraulic phenomena that would occur in commercial PWR systems in the same sequence and with approximately the same time frames and magnitudes. The information acquired from loss-of-coolant experiments (LOCE) is thus used for evaluation and development of LOCA analytical methods and assessment of the quantitative margins of safety provided by the ESFs when responding to a LOCA. The design and current experience with the LOFT facility is described in relation to the Nuclear Regulatory Commission's (NRC) research program. Expectations for use of the LOFT facility with emphasis on the types of informaion currently of greatest importance are also described.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6267439
• Report Number(s): CONF-790803-13; TRN: 79-014510
• Resource Relation: Conference: 14. intersociety energy conversion conference, Boston, MA, USA, 5 Aug 1979
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
DESIGN
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR OPERATION
SIMULATION
SPECIFICATIONS
ACCIDENTS
OPERATION
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors