Status of international collaborative efforts on selected ITER materials
Source abstract
Abstract
Abstract The paper presents an overview of the performance of refractory metals, beryllium, and copper alloys, for the international thermonuclear experimental reactor (ITER) high heat flux structures. High temperature brazing, hot isostatic pressing (HIP), friction welding, explosive bonding, and other methods were explored to join copper alloys to 316 stainless steel for first wall and limiter applications. It is concluded that the main material problems for the ITER high heat flux components are: (a) degradation of properties after the manufacturing cycle (especially for Be/Cu and Cu/stainless steel (SS) joints); (b) helium embrittlement of Be, and Cu, and; (c) radiation-induced loss of fracture toughness for Be, W, and Cu alloys.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Aluminum Alloy Microstructure Properties · Microstructure and mechanical properties
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References (17)
Show source-provided references
1. R. Matera, G. Frederici and the ITER Joint Central Team, J. Nucl. Mater. 233–237 (1996) 1710.1016/S0022-3115(96)00317-0 ↗
2. Zinkle · Nucl. Fus. Suppl. · 1994 · 5 · 163
3. Kalinin · J. Nucl. Mater. · 1996 · 233–237 · 910.1016/S0022-3115(96)00316-9 ↗
4. Odegard · J. Nucl. Mater. · 1996 · 233–237 · 4410.1016/S0022-3115(96)00303-0 ↗
5. S.A. Fabritsiev, A.S. Pokrovsky, D.J. Edwards, S.J. Zinkle, A.F. Rowcliffe, R.R. Solomon, The effect of copper-steel joining technology, with the HIP method used, on the radiation resistance of ITER copper alloys, presented at the Eighth International Conference on Fusion Reactor Materials, Sendai, Japan, 1997
6. S.A. Fabritsiev, A.S. Pokrovsky, Plasma Devices Operations 8 (1999) 110.1080/10519999908228142 ↗
7. Fabritsiev · J. Nucl. Mater. · 1998 · 258–263 · 206910.1016/S0022-3115(98)00422-X ↗
8. Fabritsiev · J. Nucl. Mater. · 1998 · 258–263 · 101510.1016/S0022-3115(98)00389-4 ↗
9. S.A. Fabritsiev, A.S. Pokrovsky, D.J. Edwards, S.J. Zinkle, A.F. Rowcliffe, Effect of irradiation temperature on the mechanical properties and structure of Cu/SS joints irradiated at low doses, presented at the Ninth International Conference on Fusion Reactor Materials, Colorado, US, 1999
10. R.D. Watson, D.L. Youchison, D.E. Dombrovski, I.B. Kupriyanov, R.N. Giniyatulin, Low cycle thermal fatigue of beryllium, in: Proceedings of the Second IEA International Workshop on Beryllium Technology for Fusion, CONE-95-9218, Wyoming, September 1995
11. A. Makhankov, I. Mazul, V. Safronov, N. Yablokov, Development and optimization of tungten armour geonutry for ITER divertor, in: Proceedings of the 20th Symposium on Fusion Technology, vol. 1, Marseille, 7–11 September 1998, p. 267
12. Linke · J. Nucl. Mater. · 1998 · 258–263 · 63410.1016/S0022-3115(98)00245-1 ↗
13. A. Gervash, R. Giniyatulin, I. Mazul, Fus. Eng. Des. (1999) (unpublished)
14. S.A. Fabritsiev, A.S. Pokrovsky, R.M. Bagautdinov, The neutron irradiation effect on the mechanical properties and structure of beryllium «Effect of Radiation on Materials, in: Proceedings of the 18th International Symposium, ASTM STP 1325, 1997
15. R. Giniyatulin, I. Mazul, R. Melder et al., In-pile thermocycling testing and post-test analysis of beryllium divertor mockup, in: Proceedings of the Third IEA Workshop on Beryllium Technology for Fusion, Japan, JAERI – conf. 98-001, October 1997, p. 221
16. Kalin · J. Nucl. Mater. · 1999 · 271–272 · 41010.1016/S0022-3115(98)00796-X ↗
17. A. Gervash, R. Giniyatulin, I. Mazul, R. Watson, Beryllium armoured mockups for fusion high heat flux application, in: Proceedings of the 20th Symposium on Fusion Technology, vol. 1, Marseille, 7–11 September 1998, p. 47