Materials compatibility studies for the Spallation Neutron Source

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The Spallation Neutron Source (SNS) is a high power facility for producing neutrons that utilizes flowing liquid mercury inside an austenitic stainless steel container as the target for a 1.0 GeV proton beam. Type 316 SS has been selected as the container material for the mercury and consequences of exposure of 316 SS to radiation, thermal shock, thermal stress, cavitation and hot, flowing mercury are all being addressed by R and D programs. In addition, corrosion studies also include evaluation of Inconel 718 because it has been successfully used in previous spallation neutron systems as a window material. Two types ... continued below

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6 p.

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DiStefano, J.R.; Pawel, S.J. & Manneschmidt, E.T. November 1, 1998.

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Description

The Spallation Neutron Source (SNS) is a high power facility for producing neutrons that utilizes flowing liquid mercury inside an austenitic stainless steel container as the target for a 1.0 GeV proton beam. Type 316 SS has been selected as the container material for the mercury and consequences of exposure of 316 SS to radiation, thermal shock, thermal stress, cavitation and hot, flowing mercury are all being addressed by R and D programs. In addition, corrosion studies also include evaluation of Inconel 718 because it has been successfully used in previous spallation neutron systems as a window material. Two types of compatibility issues relative to 316 SS/mercury and Inconel 718/mercury are being examined: (1) liquid metal embrittlement (LME) and (2) temperature gradient mass transfer. Studies have shown that mercury does not easily wet type 316 SS below 275 C. In the LME experiments, attempts were made to promote wetting of the steel by mercury either by adding gallium to the mercury or coating the specimen with a tin-silver solder that the mercury easily wets. The latter proved more reliable in establishing wetting, but there was no evidence of LME in any of the constant extension rate tensile tests either at 23 or 100 C. Inconel 718 also showed no change in room temperature properties when tested in mercury or mercury-gallium. However, there was evidence that the fracture was less ductile. Preliminary evaluation of mass transfer of either type 316 SS or Inconel 718 in mercury or mercury-gallium at 350 C (maximum temperature) did not reveal significant effects. Two 5,000 h thermal convection loop tests of type 316 SS are in progress, with specimens in both hot and cold test regions, at 300 and 240 C, respectively.

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6 p.

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INIS; OSTI as DE99000387

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  • Nuclear applications of accelerator technology, Gatlinburg, TN (United States), 20-23 Sep 1998

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  • Other: DE99000387
  • Report No.: ORNL/CP--99076
  • Report No.: CONF-980921--
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/903 | External Link
  • Office of Scientific & Technical Information Report Number: 291066
  • Archival Resource Key: ark:/67531/metadc681535

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  • November 1, 1998

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  • July 25, 2015, 2:20 a.m.

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  • Jan. 19, 2016, 7:41 p.m.

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DiStefano, J.R.; Pawel, S.J. & Manneschmidt, E.T. Materials compatibility studies for the Spallation Neutron Source, article, November 1, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc681535/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.