On calculation of the contour size of the J-integral for assessment of the structural integrity of the VVER reactor pressure vessels under emergency core cooling

Author:

Margolin B. Z.,Kostylev V. I.,Fomenko V. N.,Akbashev I. F.,Matkovsky V. V.

Publisher

Pleiades Publishing Ltd

Subject

General Engineering,General Materials Science

Reference26 articles.

1. RD EO 1.1.3.99.0871–2012. Metodika rascheta na soprotivlenie khrupkomu razrusheniyu korpusov AES s VVER-1000 pri prodlenii sroka ekspluatatsii do 60 let (RD EO 1.1.3.99.0871–2012: Procedure of calculation of brittle fracture resistance of RPV for NPP with WWER-1000 under operation up to 60 years), Moscow: Rosenergoatom, 2012.

2. Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment IAEA-TECDOC-1627, Vienna: Int. At. Energy Agency, 2010.

3. Guidelines for Integrity and Lifetime Assessment of Components and Piping in WWER Nuclear Power Plants (VERLIFE), Vienna: Int. At. Energy Agency, 2014.

4. Eshelby, J.D., The continuum theory of lattice defects, in Solid State Physics, Scits, F. and Turnbull, D., Eds., New York: Academic, 1956, vol. 3, pp. 79–144.

5. Cherepanov, G.P., Crack propagation in continuous media, J. Appl. Math. Mech., 1967, no. 31, pp. 503–512.

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