The Status of Studies on Structural Materials under High Energy Proton and Neutron Mixed Spectrum

Transcription

1 The Status of Studies on Structural Materials under High Energy Proton and Neutron Mixed Spectrum Y. Dai and W. Wagner Paul Scherrer Institut, 5232 Villigen PSI, Switzerland International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators, May 2009, Vienna AccApp2009, Vienna / Y. Dai, PSI 1

2 Introduction Outline Irradiation experiments in spallation targets Representative results of austenitic and martensitic steels Summary and Outlook AccApp2009, Vienna / Y. Dai, PSI 2

3 Introduction AccApp2009, Vienna / Y. Dai, PSI 3

4 Introduction High power spallation targets Spallation Source Power (MW) Proton energy (GeV) Target materials Main structural materials Annual damage rate ** (dpa in Fe) SINQ (CW) 0.75 (~ 1)* 0.56 Pb Zry-2 SS 316L Al-alloy ~20 SNS (pulsed) 0.7 (1.4)* 1.0 Hg SS 316L ~20 JSNS (pulsed) 0.1 (1.0)* 3.0 Hg SS 316L ~20 Spallation targets in ADS (CW) > 5(?) ~1.0 Pb or PbBi T91 SS 316 ODS steels > 50 * Maximum power to be reached ** at beam window position, at the maximum power and for a full operation year AccApp2009, Vienna / Y. Dai, PSI 4

5 Introduction Radiation damage induced microstructural changes in materials AlMg3 irradiated to 3.6 dpa at ~60 C at SINQ target SS 316 (CW) irradiated to 12.2 dpa at 343 C at Tihange 1 (PWR) Hamaguchi & Dai, JNM (2004) 958. Edwards et al. JNM 317 (2003) 32. AccApp2009, Vienna / Y. Dai, PSI 5

6 Introduction Radiation induced hardening and embrittlement effects in materials Austenitic stainless steel EC 316 LN irradiated at SINQ target Martensitic steels F82H and HT-9 irradiated to dpa at HFIR (ORNL) Stress (MPa) dpa, 285 C 7.6 dpa, 222 C 5.3 dpa, 155 C SS 316LN Tt = 22 C 4 dpa, 117 C 3 dpa, 84 C Unirr Strain (%) Dai et al. JNM 377 (2008) 109. Rowcliffe et al. JNM (1998) AccApp2009, Vienna / Y. Dai, PSI 6

7 Introduction High energy protons induced high He and H production rate in Materials Helium prodution -section of protons SS316, measured Garner, et al. (p) Ni Fe Green et al. (p) 0.4 -Section(b) Lisor-2 T91 (p) STIP-II F82H (p) E (MeV) He-to-dpa ratio In spallation targets: up-to 100 appm He / dpa In fusion reactors: appm He / dpa In fission reactors: < 1 appm He / dpa (for most of materials) AccApp2009, Vienna / Y. Dai, PSI 7

8 Introduction For developing high power advanced spallation neutron targets, it is necessary to understand: (1) the synergistic radiation effects of displacement damage, He and H on the hardening and embrittlement, and (2) liquid metal corrosion and embrittlement effects of structural materials. In order to establish spallation materials database, one irradiation experiment (for APT-Program) Program) was performed at LANSCE during and five experiments (STIP-I I to V) were done at SINQ during AccApp2009, Vienna / Y. Dai, PSI 8

9 Irradiation experiments in spallation targets AccApp2009, Vienna / Y. Dai, PSI 9

10 Irradiation experiment at LANSCE p+ / n 800 MeV p+ mainly Maloy & Sommer, IWSMT-2, AccApp2009, Vienna / Y. Dai, PSI 10

11 Irradiation experiment at LANSCE Structural materials irradiated at LANSCE up to ~13 dpa at 160 C. They are mainly: Austenitic steels: SS 316L, SS 304L FM steels: 9Cr-1Mo (mod.), 9Cr-2WTaVNb, F82H Al-alloys: Al-6061, Al5052-O Ni-alloy: Inconel 718 Welds: 316L+316L, 316L+Inconel 718, Al alloys+316l, Al-alloys+Al-alloys PIE has been conducted. AccApp2009, Vienna / Y. Dai, PSI 11

12 Irradiation STIP experiments Irradiation: P at & SINQ N spectra (STIP) ~360 rods of Pb with SS 316L/Zircaloy cladding, specimen rods 40 cm 14 cm Max. P-flux: 2.2x10 14 p/(cm 2 s). Max. fast N (>0.1 MeV) - flux: 2.0x10 14 n/(cm 2 s). 14 cm AccApp2009, Vienna / Y. Dai, PSI 12

13 Materials Austenitic steels FM steels (FMS) FMS-ODS Ni-alloy Al-alloy Zr-alloy Ta Mo, W, alloys SiCf/SiC,, CMC PAUL SCHERRER INSTITUT Irradiation experiments at SINQ (STIP) STIP-I 12 dpa 400 C 12 dpa 360 C 12 dpa 400 C 3 dpa 60 C 22 dpa < 300 C Yes (no results) STIP-II II 400 C 400 C < 400 C 400 C 6 dpa 60 C 35 dpa < 300 C 30 dpa 350 C Yes (no results) Yes (to be tested soon) STIP-III III 400 C 800 C 800 C 35 dpa < 300 C STIP-IV IV < 400 C(?) 25 dpa < 600 C(?) 25 dpa < 600 C(?) Yes (to be tested soon) AccApp2009, Vienna / Y. Dai, PSI 13 Yes Yes STIP-V 20 dpa 400 C 20 dpa 400 C 20 dpa 600 C Yes Yes 800 C Some samples irradiated in contact with liquid metals, Pb, Pb-Bi or Hg.

14 Materials Austenitic steels FM steels (FMS) FMS-ODS Ni-alloy Al-alloy Zr-alloy Ta Mo, W, alloys SiCf/SiC,, CMC PAUL SCHERRER INSTITUT Irradiation experiments at SINQ (STIP) STIP-I 12 dpa 400 C 12 dpa 360 C 12 dpa 400 C 3 dpa 60 C 22 dpa < 300 C Yes (no results) STIP-II II 400 C 400 C < 400 C 400 C 6 dpa 60 C 35 dpa < 300 C 30 dpa 350 C Yes (no results) Yes (to be tested soon) STIP-III III 400 C 800 C 800 C 35 dpa < 300 C STIP-IV IV < 400 C(?) 25 dpa < 600 C(?) 25 dpa < 600 C(?) Yes (to be tested soon) AccApp2009, Vienna / Y. Dai, PSI 14 Yes Yes STIP-V 20 dpa 400 C 20 dpa 400 C 20 dpa 600 C Yes Yes 800 C PIE has been performed on the specimens under irradiation conditions marked in red colour.

15 Representative results of austenitic and martensitic steels AccApp2009, Vienna / Y. Dai, PSI 15

16 Results: Austenitic steels tensile properties C, 17.3, 1735, C (L-type) 350 C, 17.3, 1735, C (L-type) EC316LN Tt = Ti 100 C, 4, 265, C Stress (MPa) C, 11.3, 980, C 350 C, Unirr 250 C, Unirr C, 9.7, 770, C 250 C, 7.6, 535, C 150 C, Unirr 150 C, 5.3, 335, C Strain (%) Y. Dai et al. / JNM, 377 (2008) 109 AccApp2009, Vienna / Y. Dai, PSI 16

17 Results: Austenitic steels tensile properties 316F-SA irradiated in STIP-I S. Saito et al. / JNM, 343 (2005) 253 AccApp2009, Vienna / Y. Dai, PSI 17

18 Results: Austenitic steels tensile properties Total elongation (%) STIP C 100 C 150 C TE, EC316LN TE, SS316F, at 250 C TE, JPCA, at 250 C TE, SS316L, at 250 C 250 C 300 C 350 C Neutron irradiation Irradiation Dose (dpa) Y. Dai et al. / JNM, 377 (2008) 109 As for tensile data, no great difference between STIP and neutron irradiations Data from W.L. Bell, T. Lauritzen and S. Vaidyanathan, in Proc. Topical Conf. on Ferritic Alloys for Use in Nuclear Technologies, (AIME, Warrendale, PA, 1984), p A. Kohyama, M.L. Grossbeck and G. Piatti, J. Nucl. Mater (1992) 37. G.R. Odette and G.E. Lucas, J. Nucl. Mater (1991) 572. G.R. Odette and G.E. Lucas, J. Nucl. Mater (1992) 50. J.D. Elen and P. Fenici, J. Nucl. Mater (1992) 766. F.W. Wiffen and P.J. Maziasz, J. Nucl. Mater. 103&104 (1981) S. Jitsukawa, P.J Maziasz, T. Ishiyama, L.T. Gibson and A. Hishinuma, J. Nucl. Mater (1992) 771. H. Schroeder and W. Liu, J. Nucl. Mater., (1992) 776. J.E. Pawel, D.J. Alexander, M.L. Grossbeck, A.W. Longest, A.F. Rowcliffe, G.E. Lucas, S. Jitsukawa, A. Hishinuma and K.Shiba, J. Nucl. Mater (1994) 442. AccApp2009, Vienna / Y. Dai, PSI 18

19 Results: Austenitic steels - fracture toughness L o a d ( N ) KQ=300MPa m 1/2 KQ=200MPa m 1/2 7.8 dpa, 489 ppm He irr. T: 144 DC test T: 150 DC L o a d (N ) dpa, 936 ppm He irr. T: 306 DC test T: 300 DC displacement of crosshead (mm) displacement of crosshead (mm) L o a d (N ) KQ=25MPa m 1/ dpa, 1490 appm He irr. T: 423 C test T: 400 C displacement of crosshead (mm) AccApp2009, Vienna / Y. Dai, PSI 19

20 Results: FM steels tensile properties Dai, et al. JNM, 377 (2008) 115. AccApp2009, Vienna / Y. Dai, PSI 20

21 Results: FM steels fracture toughness K Q (KJ/m 2 ) T t =100 o C T t =170 o C T t =25 o C Tt Ti T t =250 o C T t =250 o C T91, STIP-I T91,STIP-I F82H, STIP-I Optimax, STIP-I T91, STIP-III F82H, STIP-III T t =400 o C Brittle fracture Dose (dpa) AccApp2009, Vienna / Y. Dai, PSI 21

22 Results: FM steels DBTT shift DBTT SP = 0.4 DBTT CVN DBTT CVN ( C) SP CVN T i <380 C F82H T91 Optimax-A/C Optifer-V/-I Eurofer DBTT SP ( C) dpa Neutron irradiation T91 & Eurofer Displacement (dpa) Neutron irradiation data: (1) Klueh et al, J. Nucl. Mater. 218 (1995) 151; (2) Hu et al. STP 1046 (ASTM, 1990), p.453; (3) Alamo, Euromat2007. AccApp2009, Vienna / Y. Dai, PSI 22

23 Results: FM steels LBE embrittlement effects Long & Dai, to be published in JNM AccApp2009, Vienna / Y. Dai, PSI 23

24 Summary Structural materials such as austenitic and martensitic steels, Ni-, Al-, W-alloys, and ceramics have been irradiated in SINQ targets up to about 20 dpa (in steels) at temperatures up to 800 C. PIE has been conducted on a part of specimens of austenitic and martensitic steels and other alloys mostly at lower temperatures < 450 C. The results show a general trend that the degradation of mechanical properties is more pronounced after spallation irradiation as compared that after fission neutron irradiation, particularly for martensitic steels. Outlook Continue the PIE of STIP samples Continue irradiation experiments in SINQ targets Perform the PIE of the MEGAPIE target AccApp2009, Vienna / Y. Dai, PSI 24

25 Outlook: MEGAPIE PIE Irradiation parameters of the MEGAPIE target Component Max. dose (dpa) Max. Helium concentration (appm) Irradiation Temp. range ( C) T91 beam window SS 316L flow guide tube AccApp2009, Vienna / Y. Dai, PSI 25

26 Outlook: MEGAPIE PIE I0 = 1.4mA Inner surface conditions (or more): 1: highest dpa & T 2: high T, medium dpa 3: medium dpa & T 4: low dpa, medium T 5: low dpa & T, high flow 6: low dpa, T & flow C 310 C 302 C Jet flow AccApp2009, Vienna / Y. Dai, PSI 26

27 Outlook: MEGAPIE PIE Corrosion + erosion Embrittlement (irr., He, LBE) Mecha nical change Microstr uctural change Chemi cal change Association (number of conditions) OM + µ- hardness + SEM/EPMA (µ-hardness) CEA (2 cond) LANL (2 cond) PSI (2 cond) JAEA (2 cond), KAERI TEM / FEGSTEM CEA (2 cond) FZK (3 cond) PSI (2 cond) JAEA (2 cond), KAERI H and He analyses PSI (3 cond) SIMS / PS PSI (SIMS:2cond) SCK (PS:1cond) RD CEA (2 cond) Tensile test CEA (2 cond) LANL (2 cond) PSI/ENEA(3cond)* KAERI Bending test LANL (3cond) PSI (3 cond)* Small punch test ** CEA (2 cond) PSI (2 cond) CNRS (3 cond)* * Tests to be done in both Ar (or Air) and LBE environments. ** CNRS will use 8.9 mm diameter discs and the others will use 3 mm diameter discs. AccApp2009, Vienna / Y. Dai, PSI 27

28 Thank You! AccApp2009, Vienna / Y. Dai, PSI 28