Published November 1978 | Version v1
Report Open

Characterization of the material used in the project 'stress corrosion cracking in austenitic material for nuclear power reactors'. CNIITMASH/STU

Creators

Description

In the cooperation project ''Stress Corrosion Cracking in austenitic material for nuclear power reactors'' are CNIITMASH (Russia), Atomic energy (Studsvik) Sandvik AB and the Swedish Board for Technical Development involved. For the material used in the project, which is produced by Sandvik AB, has a characterization been made. The material consists of variants of SANDVIK San 70, SANDVIK San 30, SANDVIK 8R30 and 20Cr-25Ni. The following properties have been studied: Mechanical properties (at room temp. 150 deg C, 200 deg C, 350 deg C) grain sizes, chemical composition and hardness (HV 30). (author)

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Additional details

Additional titles

Original title (no language)
Spaenningskorrosion i austenitiska material foer kaernkraftreaktorer.

Publishing Information

Imprint Title
Testing in a 100 ppm Cl and 0.2 ppm O_2 sodium chloride solution at 320 deg C
Journal Page Range
22 p.
Report number
STU--75-3741

INIS

Optional Information

Notes
Imprint:Spaenningskorrosion i austenitiska material foer kaernkraftreaktorer.
Secondary number(s)
STU--77-4339.