Actions for SR's reactor tank inspection program [electronic resource] : UT development, application, and results
SR's reactor tank inspection program [electronic resource] : UT development, application, and results
- Published
- Washington, D.C. : United States. Dept. of Energy, 1990.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (8 pages) : digital, PDF file
- Additional Creators
- Westinghouse Savannah River Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Savannah River Site (SRS) has the nation's only plutonium and tritium production reactors. All three reactors have been idle for more than a year so that a variety of modifications can be made. Modifications are being carried out to enhance safety and technical systems. A 1987 decision was made to develop an inspection capability which would allow volumetric inspection of the SRS reactor tanks for the purpose of life extension. The scope of this inspection was defined to address the heat affected zones (HAZ's) of the tanks' weldments for the presence of service induced flaws, i.e., intergranular stress corrosion cracking (IGSCC). In order to be consistent with the existing practices and technology of the nuclear industry a state-of-the-art ultrasonic (UT) examination was chosen as the primary examination medium. Both ultrasonic and eddy current testing were selected as complementary methods for this application, since both can be configured to acquire test data remotely, and the test data can be digitized and stored for post-test analysis. Since intergranular stress corrosion cracking was believed to be the service-induced flaw most likely to occur adjacent to SRS's type 304 stainless steel reactor tank welds, the Savannah River Site's nondestructive testing specialists were faced with a unique challenge. Up to this point the major concentration of effort in the commercial nuclear world has been to apply ultrasonic testing techniques which were developed to detect and size IGSCC on the inside surface of piping with the search unit scanning on the outside surface of the pipe. Proven methods for detection and depth sizing IGSCC which initiated on the near surface (the surface in which the ultrasonic wave enters the metal) had not been established.
- Report Numbers
- E 1.99:wsrc-ms-90-253
E 1.99: conf-901053--4
conf-901053--4
wsrc-ms-90-253 - Subject(s)
- Other Subject(s)
- Production Reactors
- Reactor Vessels
- Welded Joints
- Stainless Steel-304
- Intergranular Corrosion
- Stress Corrosion
- Ultrasonic Testing
- Detection
- Inspection
- Reactor Safety
- Savannah River Plant
- Tanks
- Acoustic Testing
- Alloys
- Austenitic Steels
- Chemical Reactions
- Chromium Alloys
- Chromium-Nickel Steels
- Containers
- Corrosion
- Corrosion Resistant Alloys
- Heat Resistant Materials
- Heat Resisting Alloys
- High Alloy Steels
- Iron Alloys
- Iron Base Alloys
- Joints
- Materials
- Materials Testing
- National Organizations
- Nickel Alloys
- Nondestructive Testing
- Reactors
- Safety
- Stainless Steels
- Steel-Cr19ni10
- Steels
- Testing
- Us Aec
- Us Doe
- Us Erda
- Us Organizations
- Note
- Published through SciTech Connect.
01/01/1990.
"wsrc-ms-90-253"
" conf-901053--4"
"DE92017060"
Fall conference of the American Society for Nondestructive Testing, Seattle, WA (United States), 9-12 Oct 1990.
Howard, B.; McKaig, M.M. - Funding Information
- AC09-89SR18035
View MARC record | catkey: 14368902