On irradiation embrittlement and recovery annealing mechanisms of Cr–Mo–V type pressure vessel steels
Source abstract
Abstract
Surveillance specimens of 15Kh2MFA reactor pressure vessel (RPV) steel and Sv-10KhMFT weld metal were investigated using internal friction, electrical resistivity and Mössbauer spectroscopy measurements in order to obtain information on their irradiation embrittlement and recovery annealing mechanisms. Internal friction measurements showed that carbon becomes trapped by irradiation-induced defects (fluence=4.1×1019 n/cm2, E>1 MeV, T=265 °C). During the recovery annealing (450 and 475 °C/1 h) carbon does not redissolve into the solid solution. Although irradiation usually increases the electrical resistivity of the RPV steels, in this study irradiation decreased the electrical resistivity of both the base and the weld metals. This can be due to a decrease in the dislocation density or precipitation under irradiation. The annealing temperature range for recovery was 300–600 °C for the base and the weld metals according to the electrical resistivity measurements. Some evidence of irradiation-induced carbide formation was achieved by the Mössbauer spectroscopy measurements.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Muon and positron interactions and applications · Metal and Thin Film Mechanics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (26)
Show source-provided references
1. R. Havel, Reactor pressure vessel embrittlement, International Atomic Energy Agency, IAEA-TECDOC-659, 1992
2. Pythian · 1992
3. Gurovich · J. Nucl. Mater. · 1997 · 246 · 9110.1016/S0022-3115(97)00103-7 ↗
4. Böhmert · J. Nucl. Mater. · 2001 · 297 · 25110.1016/S0022-3115(01)00636-5 ↗
5. Brauer · Nucl. Eng. Des. · 1991 · 127 · 4710.1016/0029-5493(91)90039-K ↗
6. Kocik · J. Nucl. Mater. · 1990 · 172 · 12610.1016/0022-3115(90)90017-H ↗
7. K. Törrönen, Microstructural parameters and yielding in a quenched and tempered Cr–Mo–V pressure vessel steel, Technical Research Centre of Finland, Report VTT-22, 1979
8. K. Ullakko, Aging of iron based martensites at low temperatures, Helsinki University of Technology, Laboratory of Engineering Materials, Report 3, 1992
9. Nowick · 1972
10. Wertheim · Phys. Rev. Lett. · 1964 · 12 · 2410.1103/PhysRevLett.12.24 ↗
11. Genin · Trans. TMS-AIME · 1968 · 343 · 1419
12. Brauer · Hyperfine Interact. · 1990 · 56 · 156310.1007/BF02405476 ↗
13. Gridnev · Phys. Met. Metall. · 1985 · 60 · 590
14. Huffman · Phys. Stat. Sol. (a) · 1967 · 22 · 47310.1002/pssb.19670220219 ↗
15. Kuzmann · J. Phys. · 1976 · 37 · C6
16. Ron · J. Appl. Phys. · 1968 · 39 · 26510.1063/1.1655743 ↗
17. Schaaf · Acta Met. Mater. · 1992 · 40 · 37310.1016/0956-7151(92)90311-2 ↗
18. Wagenblast · J. Phys. Chem. Solids · 1962 · 23 · 22110.1016/0022-3697(62)90005-7 ↗
19. Wechler · Met. Trans. · 1989 · 20A · 263710.1007/BF02670157 ↗
20. Takahashi · J. Nucl. Sci. Technol. · 1975 · 12 · 63410.3327/jnst.12.634 ↗
21. Stanley · 1965
22. G. Brauer, R. Krause, A. Polity, Annealing studies of neutron irradiated reactor pressure vessel steels by positron annihilation, Zentralinstitut für Kernforschung Rossendorf, Report Zfk-647, 1988
23. Nakata · J. Nucl. Mater. · 1985 · 131 · 5310.1016/0022-3115(85)90424-6 ↗
24. Ghazi-Wakili · Phys. Stat. Sol. (a) · 1987 · 102 · 15310.1002/pssa.2211020115 ↗
25. Lopes Gil · J. Nucl. Mater. · 1989 · 161 · 110.1016/0022-3115(89)90456-X ↗
26. H. Hänninen, Y. Yagodzinskyy, O. Tarasenko, H.-P. Seifert, U, Ehrnsten and P. Aaltonen, in: Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems–Water Reactors, Lake Tahoe, NV, USA, September 5–9, Nace, in press