The actual properties of WWER-440 reactor pressure vessel materials obtained by impact tests of subsize specimens fabricated out of samples taken from the RPV

ASTM Special Technical Publication

Volumn 1329, Issue , 1998, Pages 145-159

  Korolev, Yuri N ^a   Kryukov, Alexander M ^a   Nikolaev, Yuri A ^a   Platonov, Pavel A ^a   Shtrombakh, Yaroslav I ^a   Langer, Reinhard ^b   Leitz, Christof ^b   Rieg, Claude Yves ^c  

^a KURCHATOV INSTITUTE   (Russian Federation)

^b SIEMENS AG   (Germany)

^c EDF R AND D   (France)

Author keywords

Ductile to brittle transition temperature; Post irradiation annealing; Radiation embrittlement; Reactor pressure vessel; Subsize impact test

Indexed keywords

ANNEALING; EMBRITTLEMENT; PRESSURE VESSELS; RADIATION DAMAGE; STEEL STRUCTURES; STEEL TESTING; STRUCTURAL ANALYSIS;

DUCTILE-TO-BRITTLE TRANSITION; REACTOR PRESSURE VESSELS (RPV);

IMPACT TESTING;

EID: 0032230750     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (5)

1. Calculation Standards for Strength of Equipment and Pipes of Nuclear Power Units, PNAE-G-7-002-86 (Erergoatomizdat, Moscow, 1989).
2. Kryukov, A., Platonov, P., Shtrombakh, Ya., Nikolaev, V., Klausnitzer, E., Leitz, C., and Rieg, C-Y., Investigation of samples taken from Kozloduy unit 2 reactor pressure vessel, Nuclear Engeneering and Design, v. 160, 1996, pp. 59-76.
3. Leitz, C., Langer, R., Platonov, P., Shtrombakh, Ya, Kryukov, A., Rybin, V., Nikolaev, V., Rieg, C-Y., Learning from investigation programmes on WWER 440/230 RPVs, 4th International Conference on Material Science Problems in NPP Equipment, v. 1, 1996, pp. 165-181.
4. Pustylnik, E.I., Statistical methods on analysis and processing of observations. ("NAUKA", Moscow, 1996).
5. Amaev, A.D., Badanin, V.I., Kryukov, A.M, Nikolaev, V.A., Rogov, M.F., and Sokolov, M.A., Use of subsize specimens for determination of radiation embrittlement of operating reactor pressure vessels, Small Specimen Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension, ASTM STP 1204, W.R.Corwin, F.M. Haggag and W.L. Server, Eds., American Society for Testing and materials, Philadelphia, 1993, pp. 424-439.