METALLURGICAL EXAMINATION OF FUEL ROD FROM PWR-1 BLANKET AT THE END OF THE SECOND SEED LIFE

Technical Report · Fri Dec 01 04:00:00 EST 1961

OSTI ID:4820964

Lynam, L R

The most highly depleted PWR Core 1 blanket fuel rod was examined after an exposure of two seed lives. The rod showed no significant changes in rod dimensions, fuel mnncrostructure, or cladding microstructure. The fission gas release was low and in agreement with experimental data obtained on irradiation tests of similar type fuel elements. The hydrogen pick-up of the Zircaloy-2 sheath was consistent with theoretically calculated values. Extrapolation of the data obtained and comparison with known experimental data show that no adverse effects are anticipated in the performance of PWR Core 1 blanket rods during Seed 3 lifetime. (auth)

• Research Organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-16-006115
• OSTI ID: 4820964
• Report Number(s): WAPD-TM-308
• Country of Publication: United States
• Language: English

Related Subjects

ADSORPTION
BLANKETS
BURNUP
CANNING
CONFIGURATION
DEFORMATION
EFFICIENCY
EQUATIONS
FISSION PRODUCTS
FUEL ELEMENTS
GASES
HYDROGEN
IRRADIATION
LEAKS
MATERIALS TESTING
MEASURED VALUES
METALLURGY
NUMERICALS
POROSITY
POWER PLANTS
PRESSURE
PWR
RADIATION EFFECTS
REACTOR CORE
REACTOR TECHNOLOGY
RODS
WATER COOLANT
ZIRCALOY