Published 1990 | Version v1
Report Restricted

Weld repair of helium degraded reactor vessel material

  • 1. Westinghouse Savannah River Co., Aiken, SC (United States)
  • 2. Westinghouse Electric Corp., Pittsburgh, PA (United States). Science and Technology Center

Description

Welding methods for modification or repair of irradiated nuclear reactor vessels are being evaluated at the Savannah River Site. A low-penetration weld overlay technique has been developed to minimize the adverse effects of irradiation induced helium on the weldability of metals and alloys. This technique was successfully applied to Type 304 stainless steel test plates that contained 3 to 220 appm helium from tritium decay. Conventional welding practices caused significant cracking and degradation in the test plates. Optical microscopy of weld surfaces and cross sections showed that large surface toe cracks formed around conventional welds in the test plates but did not form around overlay welds. Scattered incipient underbead cracks (grain boundary separations) were associated with both conventional and overlay test welds. Tensile and bend tests were used to assess the effect of base metal helium content on the mechanical integrity of the low-penetration overlay welds. The axis of tensile specimens was perpendicular to the weld-base metal interface. Tensile specimens were machined after studs were resistance welded to overlay surfaces

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92011174; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
WSRC-MS--90-298

Conference

Title
5. international symposium on environmental degradation of materials in nuclear power systems - water reactors.
Dates
25-29 Aug 1991.
Place
Monterey, CA (United States).

Optional Information

Contract/Grant/Project number
Contract AC09-89SR18035
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-910808--9.