Published 1995 | Version v1
Report Open

Irradiation-assisted stress corrosion cracking of HTH Alloy X-750 and Alloy 625

Description

In-reactor testing of bolt-loaded compact tension specimens was performed in 360 C water. New data confirms previous results that high irradiation levels reduce SCC resistance in Alloy X-750. Low boron heats show improved IASCC (irradiation-assisted stress corrosion cracking). Alloy 625 is resistant to IASCC. Microstructural, microchemical, and deformation studies were carried out. Irradiation of X-750 caused significant strengthening and ductility loss associated with formation of cavities and dislocation loops. High irradiation did not cause segregation in X-750. Irradiation of 625 resulted in formation of small dislocation loops and a fine body-centered-orthorhombic phase. The strengthening due to loops and precipitates was apparently offset in 625 by partial dissolution of γ precipitates. Transmutation of boron to helium at grain boundaries, coupled with matrix strengthening, is believed to be responsible for IASCC in X-750, and the absence of these two effects results in superior IASCC resistance in 625

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE95014553; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
14 p.
Report number
WAPD-T--3054

Conference

Title
water reactors.
Acronym
7. NACE international symposium on environmental degradation of materials in nuclear power plants
Dates
6-10 Aug 1995.
Place
Breckenridge, CO (United States).

Optional Information

Contract/Grant/Project number
Contract AC11-93PN38195
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-950816--1.