Experimental investigation of stress effect on swelling and microstructure of Fe–16Cr–15Ni–3Mo–Nb austenitic stainless steel under low-temperature irradiation up to high damage dose in the BOR-60 reactor
Source abstract
Abstract
Abstract The present paper was devoted to investigation of the stress effect on swelling and microstructure evolution of the Fe–15.8Cr–15.3Ni–2.8Mo–0.6Nb steel irradiated in the BOR-60 reactor at temperatures from 395 to 410 °C and damage doses from 79 to 98 dpa. Was found out that the stress increase leads to an increase of swelling, that can be associated with a decrease in incubation period with a practically constant swelling rate. Voids concentration increases at the first stage of irradiation when the void sizes are practically constant, and then the concentration reaches some saturation and swelling increase is caused by void growth.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (16)
Show source-provided references
1. F.A. Garner, L.R. Greenwood, D.L. Harrod, in: Sixth International Symposium on Environment Degradation of Materials in Nuclear Power Systems – Water Reactors, The Minerals, Metals, and Materials Society, 1993, p. 783
2. V.S. Neustroev, V.K. Shamardin, Ostrovsky et al, in: Proceedings of Fourth International Symposium on Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, Fontenvraud, France, vol. 1, 1998, p. 261
3. Porollo · J. Nucl. Mater. · 1998 · 258–263 · 161310.1016/S0022-3115(98)00166-4 ↗
4. V.M. Troyanov, Yu.I. Likhachev, M.Ya. Khmelevsky, et al., in: Proceedings of the 5th Russia Conference on Reactor Material Science, Dimitrovgrad, vol. 2, 1998 p. 3 (in Russian)
5. Bates · J. Nucl. Mater. · 1978 · 71 · 28610.1016/0022-3115(78)90426-9 ↗
6. D.L. Porter, F.A. Garner, ASTM STP 870, American Society for Testing and Materials, Philadelphia, 1985, p. 233
7. G. Arnand et al., in: Proceedings of the Conference on Irradiation Behavior of Metallic Materials for Fast Reactor Core Components, Ajaccio, Corsica, France (1979), Gif-sur-Ivette, 1979, p. 367
8. K. Herschbach, W. Schneider, H.J. Bergmann, ASTM STP 1046, American Society for Testing and Materials, Philadelphia, vol. 2, 1990, p. 570
9. R. Hubner, K. Ehrlich, ASTM STP 1366, American Society for Testing and Materials, West Conshohocken, PA, 2000, p. 778
10. V.A. Krasnoselov, A.N. Kolesnikov, V.I. Prokhorov et al., RIAR Preprint-16 (469) – Dimitrovgrad, 1981 (in Russian)
11. V.K. Shamardin, V.S. Neustroev, V.N. Golovanov et al., ASTM STP 1046, American Society for Testing and Materials, Philadelphia, 1990, p. 75310.1007/BF02046015 ↗
12. Neustroev · The Physics of Metals and Metallography · 1998 · 86 · 79
13. Garner · 1994 · vol. 10A
14. V.S. Neustroev, V.K. Shamardin, IAEA-TECDOC-1039, Vienna, 1998, p. 179
15. V.S. Neustroev, T.M. Bulanova, Ostrovsky et al., RIAR Proceedings, Dimitrovgrad, 1997, vol. 1 p. 15 (in Russian)
16. V.S. Neustroev, M.G. Bogolepov, V.N. Golovanov, et al., Voprosy atomnoy nauki I tehniki. Ser.: Atomnoe materialovedenie, 1 (24) (1987) 17 (in Russian)