Flux effect analysis in WWER-440 reactor pressure vessel steels
Source abstract
Abstract
Abstract The results of long term research programme concerning the determination of irradiation embrittlement dependence on fast neutron flux for WWER-440 reactor pressure vessel steels before and after annealing are presented in this paper. The study of flux effect was carried out on commercial WWER-440 steels which differ significantly in phosphorous (0.013–0.036 wt%) and copper (0.08–0.20 wt%) contents. All specimens were irradiated in surveillance channel positions under similar conditions at high ∼4 × 1012 сm−2 s−1 and low ∼6 × 1011 сm−2 s−1 fluxes (E > 0.5 MeV) at a temperature of 270 °С. The radiation embrittlement was evaluated by transition temperature shift on the basis of Charpy specimens test results. In case of low flux, the measured Tk shifts could be 25–50 °C bigger than the Tk shifts obtained from high flux data. A significant flux effect is observed in WWER-440 reactor pressure vessel steels with higher copper content (>0.13 wt%). Microstructural studies show that copper content decreases in the ferrite matrix and that there is formation of copper-enriched clusters and precipitates under irradiation and subsequent thermal annealing. Due to this fact the radiation damage does not depend on copper re-irradiation after annealing. Dependence of transition temperature shift on neutron flux is not expected for WWER-440 steels under re-irradiation after annealing.
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Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Microstructure and Mechanical Properties of Steels
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References (28)
Show source-provided references
1. Alekseenko · 1981
2. Alekssenko · 1997
3. Yu. R. Кеvorkyan, Mechanisms of radiation embrittlement for NPP reactor pressure materials, Preprint IAE-4879/11, Moscow, 1989.
4. А. Аmaev, А. Кryukov, V. Levit, М. Sokolov, Radiation stability of WWER-440 vessel materials, ASTM STR 1170, Philadelphia, 1993, 9-29. V.А. Nikolaev, L.N. Ryadkov, The role of spectrum and density of neutron flux in radiation embrittlement of 15Kh2MFA steel and weld metal. Radiation material science and structural strength of reactor materials, S-Petersburg, 2002.10.1520/STP24759S ↗
5. Nikolaev · 2002
6. Odette · ASTM STP · 1996 · 1270 · 547
7. R.B. Jones, C.J. Bolton, in: Proceeding of the 24th Water reactor Safety Information Meeting (1996), USNRC NUREG/CP-0157, vol. 2, (1997), p. 25.
8. M. Suzuchi, Y. Idei, M. Kizaki, K. Onizava, ASTM STP 1325, 1997.
9. Dochi · J. Nucl. Mater. · 1999 · 265 · 7810.1016/S0022-3115(98)00611-4 ↗
10. Yanagita · ASTM STP · 2000 · 1366 · 516
11. Xu · ASTM STP · 2000 · 1366 · 118
12. P. Petrequin, A review of formulas for prediction irrdadiation embrittlement of reactor vessel materials, AMES Report No 6, EUR 16455 EN, 1996.
13. R. Langer, R. Bartsch, J. Foehl, Irradiation Results for Different Reactors, Conference Proceedings Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
14. S. Rosinski, B. Server, Consideration of Dose Rate in development of an Embrittlement Correlation for U.S. Reactor Pressure Vessel Steels, in: Conference Proceedings, Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
15. B. Server, C. English, S. Rosinski, Critical Review of Embrittlement Attenuation Trough a Reactor Pressure Vessel Wall: Influence of Dose Rate, Conference Proceedings, Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
16. M. Suzuki, K. Onizava, Y. Idei, Sh. Iskander, Evaluation of Mechanical Properties on a Decommissioned Reactor Pressure Vessel, Conference Proceedings, Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
17. K. Dochi, N. Soneda, T. Onchi, S. Ishino, G. Odette, G. Lucas, Dose Rate Effect in Low Copper Steels Irradiated in FNR, Conference Proceedings Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
18. G.R. Odette, G.E. Lucas, R.D. Klingensmidt., Recent data and Analysis on Flux Effects on RPV Embrittlement, Conference Proceedings, Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
19. A.А. Chernobaeva, А.М. Кryukov, А.D. Аmaev, D. Yu. Еrak, P.А. Platonov, Ya.I. Shtrombakh, The role of flux effect on radiation embrittlement of vver-440 reactor pressure vessel materials, in: Proceeding of IAEA specialist meeting on irradiation embrittlement and mitigation, Kristal Goos, Russia, 2004.
20. Stoller · J. ASTM Int. · 2004 · 110.1520/JAI11355 ↗
21. Radiguet · 2005
22. Ballesteros · Prog. Nucl. Energy · 2011 · 53 · 75610.1016/j.pnucene.2011.05.022 ↗
23. Margolin · J. Nucl. Mater. · 2013 · 434 · 34710.1016/j.jnucmat.2012.11.014 ↗
24. G.R. Odette, T. Yamamoto, R.D. Klingensmidt, «On the Effect of Dose Rate on Irradiation Hardening of RPV Steels», Philos. Magaz., vol. 25, Nos. 4–7, pp. 779–797 (01.02-01.03 2005).10.1080/14786430412331319910 ↗
25. T. Williams, D. Ellis, W. O‘Connell, Dose Rate Effects in High and Low Nickel welds, Conference Proceedings, Workshop on Dose Rate Effects in Reactor Pressure Vessel Materials, Olympic Valley, CA, 2001.
26. Pareige · J. Nucl. Mater. · 1997 · 249 · 16510.1016/S0022-3115(97)00215-8 ↗
27. O. Zabusov, E. Krasikov, M. Kozodaev, A. Suvorov, P. Pareige, B. Radiguet, Redistribution of impurity and alloying elements in VVER-440 reactor pressure vessel steel due to operating factors, VANT, N 3 (83), Moscow, 2003, pp. 66–72.
28. Kryukov · J. Nucl. Mater. · 2012 · 429 · 19010.1016/j.jnucmat.2012.06.005 ↗