Study of stress corrosion cracking susceptibility of irradiated ferrite-martensitic stainless steel 07Kh12NMFB in supercritical water. Part 2. Development of corrosion crack identification technique and analysis of autoclave test results-Reference-Cited by-同舟云学术

Study of stress corrosion cracking susceptibility of irradiated ferrite-martensitic stainless steel 07Kh12NMFB in supercritical water. Part 2. Development of corrosion crack identification technique and analysis of autoclave test results

Published:2024-02-22 Issue:4(116) Volume: Page:245-259
ISSN:1994-6716
Container-title:Voprosy Materialovedeniya
language:
Short-container-title:Vopr. materialoved.

Author:

Margolin B. Z.¹,Pirogova N. E.¹,Sorokin A. A.¹,Kohonov V. I.¹,Dub A. V.²,Safonov I. A.²

Affiliation:

1. NRC «Kurchatov Institute» – CRISM «Prometey»

2. Private Enterprise for Nuclear Industry Scientific Developement «Science and Innovations»

Abstract

The studies of stress corrosion cracking have been carried out for the stainless ferritic-martensitic steel with chromium content of 12% irradiated to a damage neutron dose of ~12 dpa. This steel was chosen as a candidate material for the internals of supercritical water-cooled reactors (SWCR).The first part of the paper was devoted to autoclave testing of specially designed disk specimens under constant load in a supercritical water environment (at 450°C and 250 atm pressure). In this part of the article the developed technique for corrosion cracks identification is presented and analysis of autoclave tests results is performed.As a result of the experiments performed, the threshold stress values below which stress corrosion cracking initiation doesn’t occur. The values of threshold stresses are determined for the studied steel irradiated at temperatures of 390 and 550°C. Possible mechanisms of stress corrosion cracking of the studied steel are analyzed and directions for further research are proposed.

Publisher

FSUE CRISM Prometey

Reference7 articles.

1. Karzov, G.P., Margolin, B.Z., Shvetsova, V.A., Fiziko-mekhanicheskoe modelirovanie protsessov razrusheniya [Physical and mechanical modeling of destruction processes], St Petersburg: Politekhnika, 1993.

2. Hancock, J.W., Mackenzi, A.C., On the mechanisms of ductile failure in high-strength steels subjected to multi-axial stress state, J. Mech. Phys. Solids., 1976, V. 24 (213), pp. 147–149.

3. Klueh, R.L., Nelson, A.T., Ferritic/martensitic steels for next-generation reactors, J. Nucl. Mater., 2007, V. 371, pp. 37–52.

4. Patra, A., Mc Dowell, D. L., Continuum modeling of localized deformation in irradiated bcc materials, J. Nucl. Mater., 2013, V. 432, pp. 414–427.

5. Zinkle, S.J., Hashimoto, N., Matsukawa, Y., et al., Microstructures of irradiated and mechanically deformed metals and alloys: fundamental aspects, Materials Research Society symposia proceedings “Materials Research Society”,·2004, January.