The EBR-II materials-surveillance program. 5: Results of SURV-5.

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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. 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. ... continued below

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33 p.

Creation Information

Ruther, W.E.; Staffon, J.D.; Carlson, B.G. & Allen, T.R. January 1, 1998.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Lab., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho

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Description

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. 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 this work, the properties of these materials irradiated at 370 C to a total fluence of 3.2 {times} 10{sup 22} n/cm{sup 2} were determined. These materials are the fifth set of irradiated subassemblies to be examined as part of the SURV program (SURV-5). The properties analyzed were weight, density, microstructure, hardness, tensile and yield strength, and fracture resistance. Of all the alloys examined in SURV-5, only Berylco-25 showed any significant weight loss. Stainless steel (both 304 and 347) had the largest density decrease, although the density decrease from irradiation for all alloys was less than 0.4 percent. The microstructure of both Berylco-25 and the aluminum-bronze alloy was altered significantly. Iron- and nickel-base alloys showed little change in microstructure. Austenitic steels (304 and 347) harden with irradiation. The hardness of Inconel X750 did not change significantly with irradiation. The ultimate tensile strength of Inconel X750, 304 stainless steel, 420 stainless steel and welded 304 changed little due to a fluence increase from 2.2 {times} 10{sup 22} n/cm{sup 2} (the maximum fluence of the SURV-4 samples) to 3.2 {times} 10{sup 22} n/cm{sup 2}.

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33 p.

Notes

INIS; OSTI as DE98004589

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  • Other Information: PBD: Jan 1998

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  • Other: DE98004589
  • Report No.: ANL--98/4
  • Grant Number: W-31109-ENG-38
  • DOI: 10.2172/658149 | External Link
  • Office of Scientific & Technical Information Report Number: 658149
  • Archival Resource Key: ark:/67531/metadc706708

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • January 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • May 16, 2016, 2:09 p.m.

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Ruther, W.E.; Staffon, J.D.; Carlson, B.G. & Allen, T.R. The EBR-II materials-surveillance program. 5: Results of SURV-5., report, January 1, 1998; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc706708/: accessed November 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.