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Reduced-activation martensitic steel is a main candidate structural material for key components of advanced nuclear energy systems because of its good mechanical properties at room temperature, low neutron activation characteristics and satisfactory radiation resistance. In this work, we study the interaction between dislocations and helium-irradiation-induced defects in the steel and the effect of dislocations on the behavior of helium migration and desorption. The well-annealed samples are pre-deformed to 10% and 20% reductions in thickness by using cold rolling mill. After pre-deformation, samples are heat-treated to remove vacancy defects and retain dislocation defects. Then, the samples with reserved dislocations are irradiated with helium at room temperature (50 keV, 1×1017 He/cm2). After irradiation, the samples are characterized by synchrotron radiation grazing incident X-Ray diffraction, positron annihilation Doppler broadening spectroscopy, and thermal desorption spectroscopy. The results show that dislocations hinder the diffusion of helium and helium-vacancy complexes, and reduce the accumulation of radiation damage. Such an effect becomes more significant with the increase of dislocation density. The BCC → FCC phase transition of low activation martensitic steel occurs at 1179 K. The increase of dislocation density will lead to the forward shift of helium desorption peak induced by phase transition. The retention of helium in the undeformed sample, 10% deformed sample and 20% deformed sample is 10.3%, 15.7% and 17.9%, respectively, indicating that high density dislocations promote the retention of helium.
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Keywords:
- helium irradiation /
- dislocation /
- positron annihilation /
- thermal desorption
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图 1 低活化马氏体钢的TEM图 (a) 1013 K退火; (b) 10%变形; (c) 20%变形. 在1013 K退火后的样品中观察到少量缺陷, 将退火样品冷轧变形10%和20%发现大量位错
Figure 1. (a) TEM micrographs of the well-annealed sample, a small number of defects are observed. (b), (c) The image of the annealed specimens after cold-worked, a number of dislocations induced by cold rolling to 10% (b) and 20% (c) of their original thickness are observed.
图 2 50 keV氦离子辐照低活化马氏体钢的辐照损伤以及氦原子深度分布的SRIM模拟(dpa, 原子平均离位; appm, 原子性部分每百万)
Figure 2. Depth distribution of vacancies and helium atoms in 50 keV helium-ion irradiated low activation martensitic steel, calculated with SRIM 2013 (dpa, displacement per atom; appm, atomic parts per million).
图 3 不同形变辐照条件下低活化马氏体钢的GIXRD谱图
Figure 3. GIXRD patterns of low activation martensitic steel with different conditions.
图 4 50 keV的氦辐照低活化马氏体钢的多普勒展宽谱 (a) S-E曲线; (b) W-E曲线; (c) S-W曲线
Figure 4. Doppler broadening spectrum of low activation martensitic steel irradiated with 50 keV ion helium: (a) S-E curves, (b) W-E curves; (c) S-W curves.
图 5 50 keV的氦辐照低活化马氏体钢的多普勒展宽谱 (a) ΔS-E曲线; (b) ΔW-E线
Figure 5. Doppler broadening spectrum of low activation martensitic steel irradiated with 50 keV ion helium: (a) ΔS-E curves; (b) ΔW-E curves.
图 6 低活化马氏体钢的热脱附谱图
Figure 6. Helium thermal desorption spectra for low activation martensitic steel.
表 1 低活化马氏体钢的化学成分
Table 1. Chemical composition of the low activation martensitic steel.
元素 Cr V Ta W C Mn Si P S Fe 质量分数/% 9.100 0.190 0.200 1.500 0.120 0.400 0.025 0.003 0.003 88.459 
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表 2 同步辐射X射线衍射数据, 即不同形变辐照条件下低活化马氏体钢的2θ和FWHM
Table 2. Synchrotron radiation X-ray diffraction data, namely, 2θ and FWHM of low activation martensitic steel with different conditions.
Sample 2θ/FWHM (110) (200) (211) (220) Undeform-unirra 44.553/0.302 64.894/0.355 82.327/0.401 98.9890/0.276 Undeform-irradiate 44.500/0.416 64.653/0.473 82.167/0.610 98.780/0.366 10%-unirra 44.566/0.359 64.902/0.466 82.330/0.583 99.008/0.355 10%-irradiate 44.524/0.465 64.801/0.544 82.127/0.663 98.554/0.397 20%-unirra 44.563/0.351 64.880/0.345 82.356/0.573 98.979/0.330 20%-irradiate 44.154/0.474 64.249/0.478 82.054/0.694 98.749/0.736
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表 3 低活化马氏体钢氦的热脱附能
Table 3. Desorption temperature and desorption activation energy.
Peak Temperature/K Energy/eV Undeformed A2 1164 3.38 A3 1179 3.41 10% deformation B1 1073 3.11 B2 1128 3.27 B3 1149 3.33 20% deformation C1 1028 2.98 C2 1096 3.18 C3 1115 3.23
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[1] Baluc N, Abe K, Boutard J L, Chernov V M, Diegele E, Jitsukawa S, Kimura A, Klueh R L, Kohyama A, Kurtz R J, Lässer R, Matsui H, Möslang A, Muroga T, Odette G R, Tran M Q, van der Schaaf B, Wu Y, Yu J, Zinkle S J 2007 Nucl. Fusion 47 S696
Google Scholar
[2] Kurtz R J, Alamo A, Lucon E, Huang Q, Jitsukawa S, Kimura A, Klueh R L, Odette G R, Petersen C, Sokolov M A, Spätig P, Rensman J W 2009 J. Nucl. Mater. 386−388 411
Google Scholar
[3] Huang Q 2014 J. Nucl. Mater. 455 649
Google Scholar
[4] Niwase K, Ezawa T, Tanabe T, Kiritani M, Fujita F E 1993 J. Nucl. Mater. 203 56
Google Scholar
[5] Mansur L K, Coghlan W A 1983 J. Nucl. Mater. 119 1
Google Scholar
[6] Chernov I I, Kalashnikov A N, Kalin B A, Binyukova S Y 2003 J. Nucl. Mater. 323 341
Google Scholar
[7] Xu Q, Sugiura Y, Pan X Q, Sato K, Yoshiie T 2014 Mat. Sci. Eng. A-Struct. 612 41
Google Scholar
[8] Woodford D A, Smith J P, Moteff J 1969 J. Nucl. Mater. 29 103
Google Scholar
[9] van den Beukel A 1979 Scr. Metall. 13 83
Google Scholar
[10] Cao Q, Ju X, Guo L P, Wang B 2014 Fusion Eng. Des. 89 1101
Google Scholar
[11] van den Beukel A 2014 Chin. Phys. Lett. 31 036101
Google Scholar
[12] Sarkar D K, Bera S, Narasimhan S V, Chowdhury S, Gupta A, Nair K G M 1998 Solid State Commun. 107 413
Google Scholar
[13] Zhu T, Zhong Z H, Sato K, Song Y M, Ye F J, Wang Q Q, Dong Y, Zhang P, Yu R S, Wang B Y, Ngan A H W, Cao X Z, Xu Q 2022 Tungsten 4 212
Google Scholar
[14] Zhang Z, Zhu T, Jin S, Zhang P, Kuang P, Guo L P, An X, Wang B Y, Yu R, Zhang S, Cao X Z 2020 Fusion Eng. Des. 161 111978
Google Scholar
[15] Zhu T, Jin S, Gong Y, Lu E Y, Song L G, Xu Q, Guo L P, Cao X Z, Wang B Y 2017 J. Nucl. Mater. 495 244
Google Scholar
[16] Sabelová V, Kršjak V, Kuriplach J, Petriska M, Slugeň V, Šimeg Veterníková J 2014 J. Nucl. Mater. 450 54
Google Scholar
[17] Song Y M, Song L G, Lian X Y, Jin S X, Zhu T, Liu Y L, Zhang P, Wang B Y, Cao X Z 2023 JJAP Conference Proceedings 9 011103
Google Scholar
[18] Jin S X, Zhang P, Lu E Y, Guo L P, Wang B Y, Cao X Z 2016 Acta Mater. 103 658
Google Scholar
[19] King D A 1975 Surf. Sci. 47 384
Google Scholar
[20] Lombardo S J, Bell A T 1988 Surf. Sci. 206 101
Google Scholar
[21] Morishita K, Sugano R, Wirth B D, Diaz de la Rubia T 2003 Nucl. Instrum. Methods Phys. Res. Sect. B 202 76
Google Scholar
[22] Zhang S, Cizek J, Yao Z, Oleksandr M, Kong X, Liu C, van Dijk N, van der Zwaag S 2020 J. Alloys Compd. 817 152765
Google Scholar
[23] Morishita K, Sugano R, Wirth B D 2003 J. Nucl. Mater. 323 243
Google Scholar
[24] Xu D, Bus T, Glade S C, Wirth B D 2007 J. Nucl. Mater. 367 483
Google Scholar
[25] Zhu T, Cao X Z, Jin S X, Wu J P, Gong Y H, Lu E Y, Wang B Y, Yu R S, Wei L 2015 J. Nucl. Mater. 466 522
Google Scholar
[26] Yonemura M, Inoue K 2016 Metall. Mater. Trans. A 47 6384
Google Scholar
[27] Wang J R, Pan B C 2022 J. Nucl. Mater. 561 153540
Google Scholar
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