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Title: Materials compatibility studies for the Spallation Neutron Source

Abstract

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 atmore » 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.« less

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Energy Research, Washington, DC (United States)
OSTI Identifier:
291066
Report Number(s):
ORNL/CP-99076; CONF-980921-
ON: DE99000387; BR: KC0202060; TRN: 99:002238
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Conference
Resource Relation:
Conference: Nuclear applications of accelerator technology, Gatlinburg, TN (United States), 20-23 Sep 1998; Other Information: PBD: [1998]
Country of Publication:
United States
Language:
English
Subject:
43 PARTICLE ACCELERATORS; 36 MATERIALS SCIENCE; 07 ISOTOPE AND RADIATION SOURCE TECHNOLOGY; NEUTRON SOURCES; ACCELERATOR FACILITIES; TARGETS; MERCURY; COMPATIBILITY; STAINLESS STEEL-316; INCONEL 718; EMBRITTLEMENT; CORROSION; BUILDING MATERIALS

Citation Formats

DiStefano, J R, Pawel, S J, and Manneschmidt, E T. Materials compatibility studies for the Spallation Neutron Source. United States: N. p., 1998. Web. doi:10.2172/903.
DiStefano, J R, Pawel, S J, & Manneschmidt, E T. Materials compatibility studies for the Spallation Neutron Source. United States. https://doi.org/10.2172/903
DiStefano, J R, Pawel, S J, and Manneschmidt, E T. 1998. "Materials compatibility studies for the Spallation Neutron Source". United States. https://doi.org/10.2172/903. https://www.osti.gov/servlets/purl/291066.
@article{osti_291066,
title = {Materials compatibility studies for the Spallation Neutron Source},
author = {DiStefano, J R and Pawel, S J and Manneschmidt, E T},
abstractNote = {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.},
doi = {10.2172/903},
url = {https://www.osti.gov/biblio/291066}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Nov 01 00:00:00 EST 1998},
month = {Sun Nov 01 00:00:00 EST 1998}
}

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