Performance of ferritic alloy cladding in LMR (liquid metal reactor) mixed-oxide fuel pins in EBR-II

Conference · Thu May 01 00:00:00 EDT 1986

OSTI ID:6890736

Makenas, B J; Lawrence, L A

Mixed uranium-plutonium oxide fuel pins with candidate ferritic alloy cladding have been irradiated in the EBR-II to evaluate performance for possible Liquid Metal Reactor (LMR) application. Ferritic alloys are of considerable interest in LMR's because of their resistance to irradiation induced swelling which, in the case of austenitic alloys, has led to duct dimensional changes and interactions between the duct and pin bundle. Ferritic alloys may also possess improved resistance to environmentally assisted crack propagation when compared to austenitic alloys.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6890736
• Report Number(s): HEDL-SA-3542-FP; CONF-861102-38; ON: DE87005473
• Resource Relation: Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
EBR-2 REACTOR
FUEL CANS
FERRITIC STEELS
FUEL PINS
IRRADIATION
MIXED OXIDE FUELS
PERFORMANCE
PHYSICAL RADIATION EFFECTS
SWELLING
ALLOYS
BREEDER REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STEELS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
210500 - Power Reactors
Breeding