Preliminary report on the irradiation conditions of the HFIR JP-23 experiment

Technical Report · Fri Mar 31 23:00:00 EST 1995

DOI:https://doi.org/10.2172/114925· OSTI ID:114925

Ermi, A. M. ^[1]; Gelles, D. S. ^[2]

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1. Westinghouse Hanford Company, Richland, WA (United States)
2. Pacific Northwest Laboratory, Richland, WA (United States)

The objective of this effort was to irradiate a series of alloys over the temperature range 300 to 600{degrees}C to approximately 10 dpa in the High Flux Isotope Reactor (HFIR). The alloys covered a wide range of materials and treatments. The Japanese specimen matrix consisted of ferritic steels, vanadium alloys, copper alloys, molybdenum alloys, and titanium-aluminum compounds. The US specimen matrix consisted of vanadium alloys, 316 stainless steels, and isotopically tailored ferritic and austenitic alloys.

• Research Organization: Oak Ridge National Lab., TN (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 114925
• Report Number(s): DOE/ER--0313/17; ON: DE95013663
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ALUMINIUM ALLOYS
ATOMIC DISPLACEMENTS
AUSTENITIC STEELS
COPPER BASE ALLOYS
FERRITIC STEELS
IRRADIATION
MOLYBDENUM BASE ALLOYS
PHYSICAL RADIATION EFFECTS
PROGRESS REPORT
STAINLESS STEEL-316
TEMPERATURE RANGE 0400-1000 K
TITANIUM ALLOYS
VANADIUM BASE ALLOYS