In-reactor determination of fuel performance limitations
Book
·
OSTI ID:4350586
From international nuclear industries fair; Basel, Switzerland (16 Oct 1972). A survey of some of the most interesting fuel clad elongation, pellet stack elongation and fuel rod diameter measurements at the Halden Project is given. The results show how the different fuel design parameters, pellet lengih, fuel-to-clad gap, pellet end-shape, fuel density and a center hole will affect the fuelclad mechanical interaction and dimensional changes of fuel rods. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-29-026080
- OSTI ID:
- 4350586
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
Survey of Westinghouse nuclear fuel performance
Factors influencing growth of PWR fuel rods
ASEA--ATOM BWR: fuel design, fabrication, and performance
Book
·
Fri Dec 31 23:00:00 EST 1971
·
OSTI ID:4350952
Factors influencing growth of PWR fuel rods
Book
·
Fri Dec 31 23:00:00 EST 1971
·
OSTI ID:4325042
ASEA--ATOM BWR: fuel design, fabrication, and performance
Book
·
Fri Dec 31 23:00:00 EST 1971
·
OSTI ID:4333290