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Stress corrosion cracking of Ni-alloys for pressurized water reactors (PWRs)

The European Commission, DG XI, has published an invitation to tender for the completion of a study on stress corrosion cracking (SCC) of Ni-alloys 600, 690 and 800 for pressurized water reactors (PWRs).

The aim of the study is to:

- Assess the susceptibility of Inconel 600/690 and Incoloy 800 to SCC;
- Assess the influence of environmental factors;
- Review the SCC mitigating methods for Ni-alloys 600/690/800;
- Make recommendations for harmonization and code improvements.

Based on a detailed survey of the literature on current techniques, and taking account of existing standards related to SCC testing of Ni-alloys 600/690/800 (including evaluation and mitigating methods), the following tasks should be completed:

- Identification and assessment of national and multinational programmes dealing with SCC susceptibility and influence of environmental factors;
- Provision of recommendations for harmonization of future codes and standards (methodology used for comparative analysis and historical background of SCC identification and remedies at operating nuclear power plants (NPPs) also to be provided);
- Extension of relevant parts of the study, identified in the technical description, to VVER reactors.
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