Weld repair of helium degraded reactor vessel material
Creators
- 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.
Files
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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059157
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; EMBRITTLEMENT; GRAIN BOUNDARIES; HEAT AFFECTED ZONE; MECHANICAL PROPERTIES; REACTOR VESSELS; STEEL-CR19NI10; TENSILE PROPERTIES; THERMAL STRESSES; WELDED JOINTS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTAINERS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MICROSTRUCTURE; NICKEL ALLOYS; STAINLESS STEELS; STEELS; STRESSES
Optional Information
- Contract/Grant/Project number
- Contract AC09-89SR18035
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-910808--9.