Improvement of the Approach to Predict the Fracture Toughness of Irradiated Anticorrosive Cladding for WWER-Type Reactors-Reference-Cited by-同舟云学术

Improvement of the Approach to Predict the Fracture Toughness of Irradiated Anticorrosive Cladding for WWER-Type Reactors

Published:2018-11 Issue:6 Volume:9 Page:1237-1242
ISSN:2075-1133
Container-title:Inorganic Materials: Applied Research
language:en
Short-container-title:Inorg. Mater. Appl. Res.

Author:

Minkin A. J.,Morozov A. M.,Smirnov V. I.

Publisher

Pleiades Publishing Ltd

Subject

General Engineering,General Materials Science

Link

http://link.springer.com/article/10.1134/S2075113318060308/fulltext.html

Reference13 articles.

1. Margolin, B.Z., Shvetsova, V.A., Prokoshev, O.Yu., Kursevich, I.P., Smirnov, V.I., and Minkin, A.I., Characteristics of anticorrosive surfacing for calculation of the resistance to brittle fracture of reactor vessel material, Vopr. Materialoved., 2005, no. 2 (42), pp. 186–213.

2. Minkin, A.J., Margolin, B.Z., Kostylev, V.I., and Smirnov, V.I., Forecasting of conservative JR-curves for the material of anticorrosive surfacing of WWER reactor vessel shells taking into account the influence of neutron irradiation, Vopr. Materialoved., 2006, no. 3 (46), pp. 91–100.

3. Radiation Embrittlement of Reactor Vessel Materials. United States Regulatory Commission, Regulatory Guide V. 1.99 (Revision 2), Rockville: US Nucl. Regul. Com., 1988.

4. Prokoshev, O.Yu., Effect of technological and operational factors on embrittlement of anticorrosive cladding of WWER-type reactor vessels, Extended Abstract of Cand. Sci. (Eng.) Dissertation, St. Petersburg: Prometey, 2005.

5. Haggag, F.M. and Nanstad, R.K., Effect of Thermal Aging and Neutron Irradiation on the Mechanical Properties of Three-Wire Stainless Steel Weld Overlay Cladding, Washington, DC: Nucl. Regul. Com., 1997.