journal article·2006-09

Swelling and microstructure of pure Fe and Fe–Cr alloys after neutron irradiation to ∼26dpa at 400°C

Yu.V. Konobeev, A.M. Dvoriashin, S.I. Porollo, F.A. Garner

Journal of Nuclear Materials· Volume 355· Issue 1-3
Publisher page

Abstract

Abstract The microstructures of pure Fe and various Fe–Cr binary alloys in both the annealed and heavily cold worked conditions were investigated after irradiation to 25.8 dpa at 4 × 10 −7 dpa s −1 in the BR-10 fast reactor. Microscopy has shown that the largest swelling of 4.5% was observed in the cold worked pure iron while that of annealed Fe is only 1.7%. Additions of 2% chromium resulted in a decrease of swelling, but the swelling of cold worked Fe–2Cr alloy was still higher than that of the annealed condition. Independent of the initial starting condition, swelling in the Fe–6Cr alloy was completely suppressed. In alloys with higher chromium content swelling of 0.04–0.05% was observed only in samples irradiated in the annealed condition. There were also significant changes in dislocation and precipitate microstructure.
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 (11)

Show source-provided references
1. Gelles · J. Nucl. Mater. · 1995 · 225 · 16310.1016/0022-3115(95)00053-4 ↗
2. E.A. Little, D.A. Stow, in: Proceedings of the International Conference on Irradiation Behavior of Metallic Materials for Fast Reactor Core Components, Ajaccio, Corsica, France, 4–8 June, 1979, p. 17.
3. H. Matsui, D.S Gelles, Y. Kondo, in: R.E. Stoller, A.S. Kumar, D.S. Gelles (Eds.), Proceedings of Effect of Radiation on Materials: 15th International Symposium, ASTM STP 1125, American Society for Testing and Materials, Philadelphia, 1992, p. 928.
4. Garner · J. Nucl. Mater. · 1984 · 122–123 · 45910.1016/0022-3115(84)90641-X ↗
5. Porollo · J. Nucl. Mater. · 1998 · 256 · 24710.1016/S0022-3115(98)00043-9 ↗
6. Garner · J. Nucl. Mater. · 1997 · 245 · 12410.1016/S0022-3115(97)00016-0 ↗
7. Garner · J. Nucl. Mater. · 2000 · 276 · 12310.1016/S0022-3115(99)00225-1 ↗
8. T. Okita, N. Sekimura, F.A. Garner, L.R. Greenwood, W.G. Wolfer, Y. Isobe, in: Proceedings 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 2001 (issued on CD format).
9. F.A. Garner, N.I. Budylkin, Yu.V. Konobeev, S.I. Porollo, V.S. Neustroev, V.K. Shamardin, A.V. Kozlov, The Influence of DPA rate on Void Swelling of Russian Austenitic Stainless Steels, 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 2003, p. 647.
10. Okita · J. Nucl. Mater. · 2002 · 307–311 · 32210.1016/S0022-3115(02)01202-3 ↗
11. Dvoriashin · J. Nucl. Mater. · 2000 · 283–287 · 15710.1016/S0022-3115(00)00337-8 ↗