Application of the floating curve model for estimation of re-irradiation embrittlement of VVER-440 RPV steels

ASTM Special Technical Publication

Volumn , Issue 1366, 2000, Pages 460-470

  Nikolaev, Yuri A ^a   Nikolaeva, Alla V ^b  

^a KURCHATOV INSTITUTE   (Russian Federation)

^b NUCLEAR SAFETY INSTITUTE   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

ANNEALING; BRITTLENESS; DUCTILITY; EMBRITTLEMENT; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; PRESSURE VESSELS; RADIATION EFFECTS;

RADIATION EMBRITTLEMENT; REACTOR PRESSURE VESSEL (RPV);

STEEL STRUCTURES;

EID: 0034481887     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp12408s     Document Type: Conference Paper

References (8)

1. Alexeyenko, N.N., Amaev, A.D., Gorynin, I.V. and Nikolaev, V.A. Irradiation damage of water-water reactor vessel steels. Russia, Moscow, Energoatomizdat, 1981.
2. Korolev, Yu.N., Kryukov, A.M., Nikolaev Yu.A., et al. Assessment of irradiation response of WWER-440 welds using samples taken from Novovoronezh unit 3 and 4 reactor pressure vessels. Nuclear Engineering and Design, 1998, v. 185, pp. 309-317.
3. Korolev, Yu.N., Kryukov, A.M., Nikolaev, Yu.A., et al. 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. Small Specimen Test Techniques, ASTM STP 1329, W.R. Corwin, S.T. Rosinski, and E. van Walle, Eds. American Society for Testing and Materials, Philadelphia, 1998, pp. 145-159.
4. Amaev, A.D., Kryukov, A.M. and Sokolov, M.A. Recovery of transition temperature of irradiated WWER-440 vessel metal by annealing. Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels. ASTM STP 1170, L.E. Steele, Ed., American Society for Testing and Materials, Philadelphia, 1993, pp. 369-379.
5. Kryukov, A.M., Nikolaev, Yu.A. and Nikolaeva, A.V. Behavior of mechanical properties of nickel-alloyed reactor pressure vessel steel under neutron irradiation and post-irradiation annealing. Nuclear Engineering and Design, 1998, v. 186, p. 353-359
6. Hawthorne, J.R. Irradiation embrittlement. Treatise on Materials Science and Technology, C.L. Briant and S.K. Bunerji, Eds., 1983, v. 25, pp. 461-524.
7. Nikolaeva, A. V., Nikolaev, Yu. A. and Kryukov, A.M. The contribution of grain boundary effects to low-alloy steel irradiation embrittlement. Journal of Nuclear Materials, 1994, v. 218, pp. 85-93.
8. Leitz, C., Klausnitzer, E. and Hofmann, G. Annealing experiments on irradiated NiMoCr weld metal. Effects of Radiation on Materials. ASTM STP 1175, A.S. Kumar, D.S. Gelles, R.K. Nanstad and E.A. Little, Eds., American Society for Testing and Materials, Philadelphia, 1993, pp. 352-362.