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The EBR-II materials-surveillance program. 4: Results of SURV-4 and SURV-6

Technical Report ·
DOI:https://doi.org/10.2172/569134· OSTI ID:569134
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In March of 1965, a set of surveillance (SURV) samples was placed in the EBR-II reactor to determine the effect of irradiation, thermal aging, and sodium corrosion on reactor materials. Eight subassemblies were placed into row 12 positions of EBR-II to determine the effect of irradiation at 370 C. Two subassemblies were placed into the primary sodium basket to determine the effect of thermal aging at 370 C. For both the irradiated and thermally aged samples, one half of all samples were exposed to primary system sodium while one half were sealed in capsules with a helium atmosphere. Fifteen different structural materials were tested in the SURV program. In addition to the fifteen types of metal samples, graphite blocks were irradiated in the SURV subassemblies to determine the effect of irradiation on the graphite neutron shield. In this report, the properties of these materials irradiated at 370 C to a total fluence of 2.2 x 10{sup 22} n/cm{sup 2} (over 2,994 days) are compared with those of similar specimens thermally aged at 370 C for 2,994 days in the storage basket of the reactor. The properties analyzed were weight, density, microstructure, hardness, tensile and yield strength, impact strength, and creep.
Research Organization:
Argonne National Lab., IL (United States)
Sponsoring Organization:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
569134
Report Number(s):
ANL--98/3; ON: DE98003058
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
AGING
BERYLLIUM ALLOYS
COPPER ALLOYS
CORROSION
CORROSIVE EFFECTS
DELORO STELLITE 6
EBR-2 REACTOR
EXPERIMENTAL DATA
GRAPHITE
INCONEL X750
PHYSICAL RADIATION EFFECTS
REACTOR MATERIALS
SODIUM
STAINLESS STEELS
TANTALUM