Performance of liquid metal reactor fuel pins with D9 cladding
The use of 316 stainless steel (SS) for Liquid Metal Fast Reactor applications is limited because of its tendency to swell significantly under neutron irradiation. Consequently, a number of alloys have been proposed as advanced cladding materials including precipitation hardened alloys, ferritic materials, and titanium modified versions of austenitic 316 SS. One of the latter type of alloys is called and is similar in composition to 316 SS but with titanium additions of approx.0.25%. Three mixed-oxide (U,Pu)O/sub 2/ fuel tests containing D9-clad pins have been successfully irradiated in EBR-II. They have demonstrated significantly lower swelling for D9 than for the reference 316 SS cladding and have shown that the behavior of D9 is very similar to 316 SS with respect to other properties important to reactor design. In two of the tests (designated P43 and P44), D9 was irradiated side-by-side with various other cladding materials. Two different variations of D9 (differing primarily in molybdenum), two cladding cold work levels, and two fuel smeared densities (85% and 89% TD) were explored. The third test, P45, was made up exclusively of 20% CW D9-clad pins.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 7125012
- Report Number(s):
- HEDL-SA-3336-FP; CONF-851115-52; ON: DE87005456
- Resource Relation:
- Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 10 Nov 1985
- Country of Publication:
- United States
- Language:
- English
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ALLOY-D-9
FUEL CANS
FUEL PINS
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MICROSTRUCTURE
STAINLESS STEEL-316
SWELLING
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
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FUEL ELEMENTS
HEAT RESISTANT MATERIALS
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IRON ALLOYS
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MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
REACTOR COMPONENTS
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