POSTIRRADIATION EXAMINATION OF 17-4 PH STAINLESS STEEL CONTROL ROD DRIVE RACK FROM SM-1 REACTOR

Autor:	A.E. Richt, K.K. Klindt, W.C. Thurber
Rok vydání:	1961
Předmět:	Cracking Materials science Penetrant (mechanical electrical or structural) Nuclear reactor core Control rod fungi Metallurgy technology industry and agriculture Metallography Oak Ridge National Laboratory equipment and supplies Rod Corrosion
DOI:	10.2172/4829940
Popis:	A portion of the control rod drive system in the SM-1 Reactor, fabricated from l7-4 PH stainless steel, was examined at the Oak Ridge National Laboratory (ORNL) hot cells after successful operation in a pressurized-water environment for approximately three years. Examination included visual inspection, magnetic-particle tests, fluorescent penetrant tests, and metallography. No evidence of stress-corrosion cracking or other damage was noted. (auth)
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::016f8e645cebaaa51db7dd12265ab970 https://doi.org/10.2172/4829940 Zobrazit plný text záznamu