Electrochemical evaluation of thermal aging embrittlement of 2 1/4 Cr-1Mo steel for a nuclear pressure vessel

Yutaka Nishiyama, Kiyoshi Fukaya, Masahide Suzuki, Motokuni Eto, Tetsuo Shoji

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)

Abstract

A nondestructive test technique using an electrochemical method was investigated for evaluating thermal aging embrittlement of 2 1/4 Cr-1Mo steel for a nuclear pressure vessel. Agings were conducted at temperatures ranging from 400 to 500°C for up to 50 000 h. In the anodic polarization curve measured in calcium nitrate solution, a secondary peak, which is higher for embrittled materials than for the deembrittled ones, was observed in the passive potential region. Changes in the secondary peak can be correlated with the degree of the embrittlement evaluated by the shift in Charpy ductile-to-brittle transition temperature (△DBTT).

Original languageEnglish
Title of host publicationASTM Special Technical Publication
PublisherPubl by ASTM
Pages16-26
Number of pages11
Edition1204
ISBN (Print)0803118694, 9780803118690
DOIs
Publication statusPublished - 1993 Jan 1
Externally publishedYes
EventProceedings of the Symposium on Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension - New Orleans, LA, USA
Duration: 1992 Jan 291992 Jan 31

Publication series

NameASTM Special Technical Publication
Number1204
ISSN (Print)0066-0558

Other

OtherProceedings of the Symposium on Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension
CityNew Orleans, LA, USA
Period92/1/2992/1/31

ASJC Scopus subject areas

  • Engineering(all)

Fingerprint

Dive into the research topics of 'Electrochemical evaluation of thermal aging embrittlement of 2 1/4 Cr-1Mo steel for a nuclear pressure vessel'. Together they form a unique fingerprint.

Cite this