Design of the US-CRBRP sodium/water reaction pressure relief system

Conference · Thu Jan 01 00:00:00 EST 1976

OSTI ID:5234236

Kruger, G B; Murdock, T B; Rodwell, E; Sane, J O

Protection against intermediate sodium system overpressure from the sodium/water reaction associated with large leaks within the CRBRP Steam Generators is provided by the sodium/water reaction pressure relief system (SWRPRS). This system consists of rupture disks connected to the intermediate sodium piping adjacent to the inlet to the superheater and outlet from the evaporator modules. The rupture discs relieve into piping that leads to reaction produce separator tanks, which in turn are vented to a centrifugal separator and flare stack arranged to burn hydrogen gas exhausting into the atmosphere. Analyses have been conducted using the TRANSWRAP Computer Code to predict the system pressures and flow rates during the large leak event. Experimental tests to be conducted in the large leak test rig (LLTR) will be used to confirm the analysis techniques used in the design.

• Research Organization: General Electric Co., Sunnyvale, Calif. (USA); Westinghouse Electric Corp., Pittsburgh, Pa. (USA)
• DOE Contract Number: EY-76-C-15-2395
• OSTI ID: 5234236
• Report Number(s): CONF-760735-2; TRN: 78-005864
• Resource Relation: Conference: US/USSR steam generator seminar, Dimitrovgrad, USSR, 26 Jul 1976
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
STEAM GENERATORS
DESIGN
LEAKS
PRESSURE RELEASE
PRESSURE SUPPRESSION
RELIEF VALVES
BOILERS
BREEDER REACTORS
CONTROL EQUIPMENT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW REGULATORS
LIQUID METAL COOLED REACTORS
POWER REACTORS
REACTORS
SODIUM COOLED REACTORS
VALVES
VAPOR GENERATORS
210500* - Power Reactors
Breeding