Small break LOCA [Loss-of-Coolant Accidents] analysis for the N Reactor

Technical Report · Thu Jun 01 04:00:00 EDT 1989

OSTI ID:719908

McLaren, J M

A series of small breaks in the pressurizer vent piping and primary coolant system were analyzed. In the larger vent break case, a four-inch break, the ECCS was actuated on high confinement pressure and low primary system pressure. The smaller vent break, a two-inch break, did not cause ECCS actuation. Breaks in the primary coolant system were studied to determine if there was a break size or location that would cause the fuel to heat up prior to initiation of the ECCS. The study showed that there was no break size that would lead to fuel heatup prior to ECCS actuation. In all of the cases studied there was no core damage. 7 refs., 36 figs.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States); Westinghouse Hanford Co., Richland, WA (USA)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 719908
• Report Number(s): WHC-SP--0461; ON: TI89021278
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ECCS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
N-REACTOR
NUMERICAL DATA
PIPES
PRESSURE TUBES
REACTOR COOLING SYSTEMS
REACTOR SAFETY