| Title: | Reactor primary coolant system pipe rupture study method for detection of sensitization in stainless steel : progress report no. 44, April - June 1978 |
| Author: | Clarke, W. L. |
| Author: | General Electric Company |
| Author: | U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Metallurgy and Materials Research Branch |
| Note: | Washington, D.C. : U.S. Nuclear Regulatory Commission, 1978., 1978 |
| Link: | page images at HathiTrust |
| No stable link: | This is an uncurated book entry from our extended bookshelves, readable online now but without a stable link here. You should not bookmark this page, but you can request that we add this book to our curated collection, which has stable links. |
| Subject: | Nondestructive testing |
| Subject: | Nuclear reactors |
| Subject: | Stainless steel -- Fatigue |
| Other copies: | Look for editions of this book at your library, or elsewhere. |
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