DESIGN, FABRICATION, AND IRRADIATION OF SUPERHEAT FUEL ELEMENT SH-4B IN VBWR
Technical Report
·
OSTI ID:4808948
The design, fabrication, and irradiation results are described for a 0.028-inch thick 304 stainless clad fuel element (SH-4B) exposed in the Vallecitos Boiling Water Reactor loop under superheat conditions. During the exposure, a maximum steam temperature of 900 deg F was obtained, or 350 deg F superheat. The fuel element was removed due to the occurrence of a defect and the subsequent release of activity in the loop. Post-irradiation examination revealed stress eorrosion craeking was responsible for the jacket failure, presumably from a combination of abnormally high water seepage in the loop and chloride ion concentration during reactor exposure. As a result of this test, information was obtained which will be helpful in establishing superheat fuel design criteria. (auth)
- Research Organization:
- General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
- NSA Number:
- NSA-16-011223
- OSTI ID:
- 4808948
- Report Number(s):
- GEAP-3796
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BOILING
CANNING
CHLORIDES
CONTAMINATION
COOLANT LOOPS
CORROSION
CRACKS
DEFECTS
FABRICATION
FAILURES
FUEL ELEMENTS
GAS COOLANT
HIGH TEMPERATURE
IMPURITIES
IN PILE LOOPS
IONS
IRRADIATION
JACKETS
LEAKS
MATERIALS TESTING
MOCKUP
PLANNING
POWER PLANTS
RADIOACTIVITY
REACTOR TECHNOLOGY
STAINLESS STEELS
STEAM
STRESSES
SUPERHEATING
THERMAL STRESSES
THICKNESS
VBWR
WATER COOLANT
CANNING
CHLORIDES
CONTAMINATION
COOLANT LOOPS
CORROSION
CRACKS
DEFECTS
FABRICATION
FAILURES
FUEL ELEMENTS
GAS COOLANT
HIGH TEMPERATURE
IMPURITIES
IN PILE LOOPS
IONS
IRRADIATION
JACKETS
LEAKS
MATERIALS TESTING
MOCKUP
PLANNING
POWER PLANTS
RADIOACTIVITY
REACTOR TECHNOLOGY
STAINLESS STEELS
STEAM
STRESSES
SUPERHEATING
THERMAL STRESSES
THICKNESS
VBWR
WATER COOLANT