Fuel adjacency effects on fast reactor cladding mechanical properties. [LMFBR]

Conference · Wed Dec 06 00:00:00 EST 1978

OSTI ID:6209814

Hunter, C. W.; Johnson, G. D.

Simulated transient tests were conducted on 234 cladding specimens from EBR-II irradiated mixed oxide fuel pins; approximately 75% of the specimens were from the fuel column region, with the remainder from the plenum and below the fuel column. The cladding specimens were taken from the N-E, N-F,, PNL-9, PNL-10, PNL-11, P-23A, P-23B, P-23C, and WSA-3 fuel pins irradiated at 15.2 to 37 KW/cm to burnup levels from 11 to 110 MWd/Kg. All the fuel pins used 20% cold worked Type 316 stainless steel cladding. Irradiation temperatures ranged from 370 to 725/sup 0/C with a peak fluence of 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV).

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 6209814
• Report Number(s): HEDL-SA-1609; CONF-790306-21; TRN: 79-015652
• Resource Relation: Conference: International conference on fast breeder reactor performance, Monterey, CA, USA, 5 Mar 1979
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
FUEL CANS
PHYSICAL RADIATION EFFECTS
TRANSIENT OVERPOWER ACCIDENTS
LMFBR TYPE REACTORS
STAINLESS STEEL-316
DUCTILITY
FUEL PINS
YIELD STRENGTH
ACCIDENTS
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
STAINLESS STEELS
STEELS
TENSILE PROPERTIES
210500* - Power Reactors
Breeding
360106 - Metals & Alloys- Radiation Effects