Application of the reconstituted subsize specimens for assessment of irradiation embrittlement of RPV steels

ASTM Special Technical Publication

Volumn , Issue 1418, 2002, Pages 151-178

  Korolev, Yury N ^a   Shtrombakh, Yaroslav I ^a   Nikolaev, Yury A ^a   Krasikov, Yevgeny A ^a   Platonov, Pavel A ^a  

^a KURCHATOV INSTITUTE   (Russian Federation)

Author keywords

Ductile to brittle transition temperature; Radiation embrittlement; Reactor pressure vessel; Samples; Specimen reconstitution; Subsize impact bend specimens; Templets

Indexed keywords

ANNEALING; BRITTLENESS; COPPER; DUCTILITY; EMBRITTLEMENT; IRRADIATION; MACHINING; PHOSPHORUS; PRESSURE VESSELS; RADIATION EFFECTS;

SUBSIZE IMPACT BEND SPECIMENS;

WELDED STEEL STRUCTURES;

EID: 0036403452     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp10819s     Document Type: Conference Paper

References (17)

1. Korolev, Yu.N., Kryukov, A.M., Nikolaev, Yu.A., Platonov, P.A., Shtrombakh, Ya.I., Langer, R., Leitz, C., and Rieg, C.-Y. "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, West Conshohochen, PA, 1998, pp. 145-159.
2. Nikolaev, Yu.A., and Nikolaeva, A.V. "Application of the floating curve model for estimation of re-irradiation embrittlement of VVER-440 RPV steels", Effects of Radiation on Materials, ASTM STP 1366, M.L. Hamilton, A.S. Kumar, S.T. Rosinski and M.L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohochen, PA, 2000, pp. 460-470.
3. Nikolaeva, A.V., Nikolaev, Yu.A., and Kryukov, A.M., "Grain boundary embrittlement due to reactor pressure vessel annealing", Journal of Nuclear Materials, Vol. 211, 1994, pp. 236-243.
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. Nikolaev, Yu.A., Nikolaeva, A.V., Kryukov, A.M., Levit, V.I., and Korolev, Yu.N., "Radiation embrittlement and thermal annealing behavior of Cr-Ni-Mo reactor pressure vessel materials", J. Nuclear Materials, Vol. 226, 1995, pp. 144-155.
6. Korolev, Yu.N., Kryukov, A.M., Nikolaev, Yu.A., Platonov, P.A., Shtrombakh, Ya.I., Langer, R., Leitz, C., and Rieg, C.-Y., "Assessment of irradiation response of WWER-440 welds using samples taken from Novovoronezh unit 3 and 4 reactor pressure vessels", Nuclear Engineering and Design, Vol. 185, 1998, pp. 309-317.
7. Korolev, Y., Kryukov, A., Nikolaev, Y., Platonov, P., Shtrombakh, Y., Langer, R., Leitz, C., Rieg, C.Y., and Nikolaev, V., "The properties of WWER-440 type reactor pressure vessel steels cut out from operated units", Nuclear Engineering and Design, Vol. 195, 2000, pp. 137-142.
8. Hawthorne, J.R., "Significance of nickel and copper content to radiation sensitivity and postirradiation heat-treatment recovery of reactor-vessel steels", Materials Engineering Associates, Inc., Lanham, MD (USA), NUREG/CR-2948, November 1982. - 24 p.
9. "Calculation standards of strength of equipment and pipes of nuclear power units", PNAE-G-002-86. Energoatomizdat, Moscow, 1989.
10. Nanstad, R.K., Haggag, F.M., McCabe, D.E., Iskander, S.K., Bowman, K.O., and Menke, B.H., "Irradiation effects on fracture toughness of two high-copper submerged-arc welds", HSSI Series 5. ORNL Report, NUREG/CR-5913, ORNL/TM-12156/V1, Oak Ridge National Laboratory, Oak Ridge, TN, 1992.
11. Nanstad, R.K., McCabe, D.E. and Swain R.L., "Evaluation of variability in material properties and chemical composition for Midland reactor weld WF-70", Effects of Radiation on Materials, ASTM STP 1325, R.K. Nanstad, M.L. Hamilton, F.A. Garner and A.S. Kumar, Eds., American Society for Testing and Materials, Philadelphia, 1999, pp. 125-156.
12. 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 Engineering and Design, Vol. 160, 1996, pp. 59-76.
13. 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.
14. "Validation of the correlation dependencies between the ductile-to-brittle transition temperature determined from tests of subsized specimens and from standard Charpy specimens", Report RRC "Kurchatov Institute" and CRISM "Prometey". Moscow 1992.
15. "Validation of definition technique of pressure vessel steel ductile-to-brittle transition temperature by the results of subsize specimens impact bend testing", IAE-TECDOC No 60/739, Institute of Atomic Energy, Moscow, 1990.
16. "Correlation between critical brittleness temperature values defined by testing of standard and subsize specimens", IAE-TECDOC No 60/862, Institute of Atomic Energy, Moscow, 1992.
17. "Technique for ductile-to-brittle transition temperature definition using the results of subsize specimen testing", IAE-TECDOC No 60/854, Institute of Atomic Energy, Moscow, 1992.