Analysis of the U. S. large leak test program Series I sodium--water reaction test results. [LMFBR]

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

OSTI ID:6018622

Sane, J O; Regimbal, J J; Fairbairn, J A; Meyer, R A

A computer code for modeling Liquid Metal Fast Breeder Reactor (LMFBR) Steam Generator (SG) leaks has been partially validated. This was accomplished by comparing code results with data from large leak Sodium/Water Reaction (SWR) tests conducted at the Energy Technology Engineering Center (ETEC). In each of six tests, a Double-Ended Guillotine (DEG) rupture of an SG tube was produced in a sodium-filled SG at typical operating conditions. The primary purpose of these tests was to provide data for validation of the TRANSWRAP (Transient Sodium Water Reaction Analysis Program) code. Primary areas of concern are the leaksite pressure history, pressures at various locations throughout the system, and expulsion of reaction products through the relief system. Agreement with TRANSWRAP results was found to be remarkably good.

• Research Organization: General Electric Co., Sunnyvale, CA (USA)
• DOE Contract Number: EY-76-C-03-0893-010
• OSTI ID: 6018622
• Report Number(s): GEFR-SP-165; CONF-790816-11; TRN: 79-015651
• Resource Relation: Conference: International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
STEAM GENERATORS
MOLTEN METAL-WATER REACTIONS
LEAKS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
MATHEMATICAL MODELS
SIMULATION
TEST FACILITIES
BOILERS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
REACTORS
VAPOR GENERATORS
210500* - Power Reactors
Breeding