Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300°C
Source abstract
Abstract
Abstract High chromium ferritic/martensitic (F/M) steels are considered as the most promising structural materials for accelerator driven systems (ADS). One drawback that needs to be quantified is the significant hardening and embrittlement caused by neutron irradiation at low temperatures with production of spallation elements. In this paper irradiation effects on the mechanical properties of F/M steels have been studied and comparisons are provided between two ferritic/martensitic steels, namely T91 and EUROFER97. Both materials have been irradiated in the BR2 reactor of SCK-CEN/Mol at 300 °C up to doses ranging from 0.06 to 1.5 dpa. Tensile tests results obtained between −160 °C and 300 °C clearly show irradiation hardening (increase of yield and ultimate tensile strengths), as well as reduction of uniform and total elongation. Irradiation effects for EUROFER97 starting from 0.6 dpa are more pronounced compared to T91, showing a significant decrease in work hardening. The results are compared to our latest data that were obtained within a previous program (SPIRE), where T91 had also been irradiated in BR2 at 200 °C (up to 2.6 dpa), and tested between −170 °C and 300 °C. Irradiation effects at lower irradiation temperatures are more significant.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear reactor physics and engineering
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References (23)
Show source-provided references
1. Mansur · J. Nucl. Mater. · 2004 · 329–333 · 16610.1016/j.jnucmat.2004.04.016 ↗
2. H. Ait Abderrahim, D. De Bruyn (Eds.), MYRRHA Pre-Design File – Draft 2, Report R-4234, Studiecentrum voor Kernenergie – Centre d’Etude de l’Energie Nucléaire, 2005, Belgium.
3. Klueh · 2001
4. Alamo · J. Nucl. Mater. · 2000 · 283–287 · 35310.1016/S0022-3115(00)00076-3 ↗
5. Lindau · Fus. Eng. Des. · 2002 · 61&62 · 65910.1016/S0920-3796(02)00178-3 ↗
6. Maloy · J. Nucl. Mater. · 2006 · 356 · 6210.1016/j.jnucmat.2006.05.024 ↗
7. Dubuisson · J. Nucl. Mater. · 1993 · 205 · 17810.1016/0022-3115(93)90080-I ↗
8. Alamo · J. Nucl. Mater. · 2007 · 367–370 · 5410.1016/j.jnucmat.2007.03.166 ↗
9. Y amamoto · J. Nucl. Mater. · 2006 · 356 · 2710.1016/j.jnucmat.2006.05.041 ↗
10. Patriarca · Nucl. Technol. · 1976 · 28 · 516
11. Schneider · Foundary Trades J. · 1960 · 108 · 562
12. M. Weber, MIRE-CR-irradiation Report NT.57/F040112/0/MW/MM/AA.rw, SCK-CEN Internal Report, 2004.
13. E. Lucon, A. Almazouzi, Mechanical response to irradiation for three high-Cr martensitic steels (EM10, T91, HT9)-Final Report: specimens irradiated to 2.6 and 3.6dpa, SCK•CEN Report BLG-986, 2004.
14. M. Matijasevic, A. Almazouzi, Effect of the chemical composition on the mechanical and microstructural behaviour of Fe–9Cr of ferritic/martensitic steels after n-irradiation at 300°C, submitted for publication.
15. Rowcliffe · J. Nucl. Mater. · 1998 · 258–263 · 127510.1016/S0022-3115(98)00163-9 ↗
16. Klueh · J. Nucl. Mater. · 1981 · 103&104 · 1275
17. A.L. Bement, in: Proceedings of ICSMA 2, vol. 2. Asilomar CA, 1970, p. 693.
18. Hashimoto · Fus. Sci. Technol. · 2006 · 44 · 49010.13182/FST44-490 ↗
19. Clausing · J. Nucl. Mater. · 1986 · 141–143 · 97810.1016/0022-3115(86)90128-5 ↗
20. T.L. Anderson, D. Steinstra, R.H. Dodds, Fracture Mechanics, vol. 24, ASTM STP 1207, ASTM, 1994, p. 185.
21. Ruggeri · Eng. Fract. Mech. · 1998 · 60 · 1910.1016/S0013-7944(98)00001-0 ↗
22. E. Lucon, Mechanical properties of the European reference RAFM steel (EUROFER 97) before and after irradiation at 300°C (0.3–2dpa), SCK-CEN Report BLG-962, 2003.
23. Lucon · J. Nucl. Mater. · 2007 · 367–370 · 57510.1016/j.jnucmat.2007.03.037 ↗