The Comparative Analysis and Verification of the Engineering Methods for Considering the Shallow Crack Effect for the Prediction of the Fracture Toughness of the Materials for Nuclear Reactor Pressure Vessels-Reference-Cited by-同舟云学术

The Comparative Analysis and Verification of the Engineering Methods for Considering the Shallow Crack Effect for the Prediction of the Fracture Toughness of the Materials for Nuclear Reactor Pressure Vessels

Published:2020-11 Issue:6 Volume:11 Page:1462-1480
ISSN:2075-1133
Container-title:Inorganic Materials: Applied Research
language:en
Short-container-title:Inorg. Mater. Appl. Res.

Author:

Kostylev V. I.,Margolin B. Z.

Publisher

Pleiades Publishing Ltd

Subject

General Engineering,General Materials Science

Link

http://link.springer.com/content/pdf/10.1134/S2075113320060106.pdf

Reference46 articles.

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2. Gorynin, I.V., Ignatov, V.A., Zvezdin, Y.I., and Timofeev, B.T., Brittle fracture resistance of welded high pressure vessels, Int. J. Pressure Vessels Piping, 1988, vol. 33, pp. 317–327.

3. Timofeev, B.T. and Anikovsky, V.V., Brittle fracture toughness Experimental estimation of RPV materials and their welds containing shallow cracks, Int. J. Pressure Vessels Piping, 1994, vol. 57, pp. 297–304.

4. Alekseenko, N.N., Amaev, A.D., Gorynin, I.V., and Nikolaev, V.A., Radiation Damage of Nuclear Power Plant Pressure Vessel Steels, La Grange Park, IL: Am. Nucl. Soc., 1997.

5. Theiss, T.J., Shum, D.K.M., and Rolf, S.T., Experimental and analytical investigation of the shallow-flaw effect in reactor pressure vessels, in USNRC Report NUREG/CR-5886 (ORNL/TM-12115), Washington, DC: US Nucl. Regul. Com., 1992.