Impact of technological parameters of arc deposition of an anti-corrosion layer in the vessel of WWER-1000 reactor on residual stress distribution

Author:

Makhnenko O.V., ,Kostenevich O.S.,

Publisher

International Association Welding

Subject

Mechanical Engineering

Reference24 articles.

1. 1. (2003) PNAE G-7-009-89: Equipment and pipelines of nuclear power plants. Welding and surfacing, basic provisions. Moscow [in Russian].

2. 2. (1982) Welded vessel 1152.02.70.000. Appendix to pressure vessel certificate 1152.02.70.000 D7, ZNPP, bl. 1 [in Russian].

3. 3. Titova, T.I.,Shulgan, N.A. (2013) Improvement of quality of welded joints and deposited surfaces of NPP equipment OJSC production "Izhorskie zavody. In: Proc. of Conf. on Ensuring the Safety of NPP with WWER, St.-Petersburg, Gidropress [in Russian]. http://www.gidropress.podolsk.ru/files/proceedings/mntk2013/autorun/article95ru.htm

4. 4. Iradj, Sattari-Far, Magnus, Andersson (2006) Cladding effects on structural integrity of nuclear components. SKI Report 2006:23, ISSN 1104-1374, ISRN SKI-R-06/23-SE.

5. 5. Katsuyama, J., Udagawa, M., Nishikawa, H. et al. (2010) Evaluation of weld residual stress near the cladding and j-weld in reactor pressure vessel head for the assessment of PWSCC behavior. Japan Society of Maintenology. E-J. of Advanced Maintenance, 2, 50-64.

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