Basic results of the Russian WWER-1000 surveillance program

Nuclear Engineering and Design

Volumn 173, Issue 1-3, 1997, Pages 333-339

  Kryukov, A M ^a   Nikolaev, Yu A ^a   Planman, T ^b   Platonov, P A ^a  

^a KURCHATOV INSTITUTE   (Russian Federation)

^b VTT TECHNICAL RESEARCH CENTRE OF FINLAND   (Finland)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0347052958     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(97)00112-x     Document Type: Article

References (6)

1. Amaev, A.D., Kryukov, A.M., Levit, V.I., Sokolov, M.A., 1993. In: Steele, L.E. (Ed.), Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels, ASTM STP 1170. American Society for Testing and Materials, Philadelphia, PA, pp. 9-379.
2. Anon., 1989. Calculation Standards for Strength of Equipment and Pipes of Nuclear Power Units, PNAE-G-7-002-86. Erergoatomizdat, Moscow.
3. Nikolaev, Yu.A., Nikolaeva, A.V., Kryukov, A.M., Levit, V.I., Korolyov, Yu.N., 1995. Radiation embrittlement and thermal annealing behaviour of Cr-Ni-Mo reactor pressure vessel materials. J. Nucl. Mater. 226, 144-155.
4. Nikolaev, Yu.A., Korolyov, Yu.N., Kryukov, A.M., Levit, V.I., Nikolaeva, A.V., Chernobaeva, A.A., Vishkarev, O.M., Nosov, S.I., 1996. Radiation resistance of reactor pressure vessel materials alloyed with nickel. Atomnaya Energiya 80 (1), 33-36.
5. Nikolaev, Yu.A., Nikolaeva, A.V., 1996. Embrittlement of low-alloyed steels due to impurity segregation at intergranular boundaries. Mater. Sci. Forum 207-209, 653-656.
6. Nikolaeva, A.V., Nikolaev, Yu.A., Kryukov, A.M., 1994. The contribution of grain boundary effects to low-alloy steel irradiation embrittlement. J. Nucl. Mater. 218, 85-93.