Clinch River Breeder Reactor Plant Steam Generator Few Tube Test model post-test examination

Conference · Wed Mar 11 04:00:00 EST 1981

OSTI ID:6593402

Impellezzeri, J R; Camaret, T L; Friske, W H

The Steam Generator Few Tube Test (FTT) was part of an extensive testing program carried out in support of the Clinch River Breeder Reactor Plant (CRBRP) steam generator design. The testing of full-length seven-tube evaporator and three-tube superheater models of the CRBRP design was conducted to provide steady-state thermal/hydraulic performance data to full power per tube and to verify the absence of multi-year endurance problems. This paper describes the problems encountered with the mechanical features of the FTT model design which led to premature test termination, and the results of the post-test examination. Conditions of tube bowing and significant tube and tube support gouging was observed. An interpretation of the visual and metallurgical observations is also presented. The CRBRP steam generator has undergone design evaluations to resolve observed deficiences found in the FFTM.

• Research Organization: General Electric Co., Sunnyvale, CA (USA); Rockwell International Corp., Canoga Park, CA (USA)
• DOE Contract Number: AM03-76SF00893
• OSTI ID: 6593402
• Report Number(s): CONF-810615-1
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BOILERS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
PERFORMANCE TESTING
POWER REACTORS
REACTORS
SODIUM COOLED REACTORS
STEAM GENERATORS
TEST FACILITIES
TESTING
TUBES
VAPOR GENERATORS