高劑量氦離子輻照對新型中子增殖鈹鎢合金表面結構的影響

劉平平; 胡文; 宋健; 賈玉梅; 詹倩; 萬發榮

doi:10.13374/j.issn2095-9389.2019.07.08.008

高劑量氦離子輻照對新型中子增殖鈹鎢合金表面結構的影響

doi: 10.13374/j.issn2095-9389.2019.07.08.008

北京科技大學材料科學與工程學院，北京 100083

基金項目: 國家自然科學基金資助項目（U1637210，11775018，51601012）

詳細信息

通訊作者:
E-mail：ppliu@ustb.edu.cn

中圖分類號: TG146.4；O469
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出版歷程
- 收稿日期: 2019-07-08
- 刊出日期: 2020-01-01

Effect of high dose helium ion irradiation on the surface microstructure of a new neutron multiplying Be?W alloy

School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China

More Information

Corresponding author: E-mail: ppliu@ustb.edu.cn

摘要

摘要: 為了確保未來核聚變反應堆的氘氚自持燃燒必需采用中子增殖材料來得到合適的氚增值比。金屬鈹被認為是最有前途的核聚變反應堆固態中子倍增材料，但其熔點低，高溫抗輻照腫脹性能差，因此需要尋找和研發具有更高熔點和更耐輻照腫脹的新型中子增殖材料以滿足更先進的聚變堆要求。本研究嘗試提出并制備了一種更高熔點的鈹鎢合金（Be₁₂W），通過X射線和掃描電子顯微鏡對它的相組成和表面結構進行分析。對新型鈹鎢合金進行高劑量的氦離子輻照，發現合金表面一次起泡的平均尺寸約為0.8 μm，面密度約為2.4×10⁷ cm^?2，而二次起泡的平均尺寸約為80 nm，面密度約為1.28×10⁸ cm^?2。分析氦輻照引起的表面起泡及其機制，并與純鈹和鈹鈦合金表面起泡的情況進行了對比。
- 氚自持 /
- 中子增殖 /
- 氦泡 /
- 鈹金屬間化合物 /
- 核聚變
Abstract: A neutron multiplier must be employed to obtain the proper tritium breeding rate and ensure the self-sustaining combustion of deuterium and tritium in fusion reactors, which represents a new and powerful solution for the energy problem. Several researchers have proposed the use of beryllium, an outstanding nuclear metal, as a promising solid neutron multiplier in the helium-cooled ceramic breeder (HCCB) test blanket module (TBM) of the Chinese TBM program. In this module, beryllium will be subjected to high-dose irradiation with high-energy neutrons during services in reactor to produce a large number of helium ions and significant irradiation damage resulting in extreme performance degradation. Unfortunately, the metal’s low melting point and poor irradiation swelling resistance at high temperatures limit its usage in the DEMO reactor. Thus, finding or developing a new neutron multiplier with a higher melting point and better ability to resist irradiation swelling than beryllium in advanced fusion reactors is an important undertaking. Knowledge of the characteristics of the microstructural changes of beryllium and/or beryllium alloys under irradiation is an important factor contributing to the understanding of the degradation of their physical-mechanical properties. In this study, a new beryllium tungsten alloy (Be₁₂W) with a high melting point was proposed and fabricated by hot isostatic pressing. The phase composition and surface structure of Be₁₂W were then analyzed by X-ray and scanning electron microscopy. The Be₁₂W alloy was irradiated with 30 keV He⁺ ions at room temperature at a dose of 1×10¹⁸ ions·cm^?2 and ion fluence of 0.2 μA. Microstructural changes and the types of helium gas-filled blisters that developed on the surface of the alloy after irradiation were subsequently investigated. Blisters with an average size of 0.8 μm and in-plane number density of 2.4×10⁷ cm^?2 initially develops, followed by blisters with an average size of about 80 nm and in-plane number density of 1.28×10⁸ cm^?2.
- tritium self-sustaining /
- neutron multiplier /
- helium blister /
- beryllium intermetallic compounds /
- fusion

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圖 1 鈹鎢合金相圖以及Be₁₂W的結構示意圖

Figure 1. Phase diagram of Be?W binary alloy and structure schematic of Be₁₂W

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圖 2 SRIM計算的氦離子在鈹鎢合金中的分布

Figure 2. Content profile of helium in the Be?W alloy calculated by SRIM

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圖 3 鈹鎢合金表面結構（a）及局部放大圖（b）

Figure 3. Surface structure of Be?W alloy (a) and partial enlarged morphology (b)

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圖 4 鈹鎢合金的相組成

Figure 4. Phase composition of Be?W alloy

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圖 5 氦離子輻照后鈹鎢合金的表面結構.（a）二次起泡；（b）部分一次起泡破裂

Figure 5. Surface structure of helium ion irradiated Be?W alloy (a) and broken of the first blister (b)

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圖 6 氦離子輻照下材料表面起泡示意圖

Figure 6. Schematic diagram of materials surface blistering under helium ion irradiation

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圖 7 氦離子輻照后鈹鎢合金的表面起泡。（a）表面起泡尺寸分布；（b）表面2次起泡尺寸分布

Figure 7. Surface blister of helium ion irradiated Be?W alloy: (a) size distribution of blister on Be?W alloy surface; (b) size distribution of secondary blister on the surface

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參考文獻(29)

[1]	Freidberg J. Plasma Physics and Fusion Energy. Beijing: Science Press, 2010 Freidberg Jeffrey. 等離子體物理與聚變能. 北京: 科學出版社, 2010
[2]	Wang N Y. Fusion Energy and Its Future. Beijing: Tsinghua University Press, 2001 王乃彥. 聚變能及其未來. 北京: 清華大學出版社, 2001
[3]	Rebut P H. ITER: the first experimental fusion reactor. Fusion Eng Des, 1995, 30(1-2): 85 doi: 10.1016/0920-3796(94)00403-T
[4]	Barabash V, Peacock A, Fabritsiev S, et al. Materials challenges for ITER–current status and future activities. J Nucl Mater, 2007, 367-370: 21 doi: 10.1016/j.jnucmat.2007.03.017
[5]	Hao J K. Fusion Reactor Materials. Beijing: Chemical Industry Press, 2007 郝嘉琨. 聚變堆材料. 北京: 化學工業出版社, 2007
[6]	Yu J N. Irradiation Effect of Materials. Beijing: Chemical Industry Press, 2007 郁金南. 材料輻照效應. 北京: 化學工業出版社, 2007
[7]	Wan F R. Irradiation Damage of Metal Materials. Beijing: Science Press, 1993 萬發榮. 金屬材料的輻照損傷. 北京: 科學出版社, 1993
[8]	Raffray A R, Akiba M, Chuyanov V, et al. Breeding blanket concepts for fusion and materials requirements. J Nucl Mater, 2002, 307-311: 21 doi: 10.1016/S0022-3115(02)01174-1
[9]	Vladimirov P, Bachurin D, Borodin V, et al. Current status of beryllium materials for fusion blanket applications. Fusion Sci Technol, 2014, 66(1): 28 doi: 10.13182/FST13-776
[10]	Giancarli L M, Abdou M, Campbell D J, et al. Overview of the ITER TBM Program. Fusion Eng Des, 2012, 87(5-6): 395 doi: 10.1016/j.fusengdes.2011.11.005
[11]	Feng K M, Pan C H, Zhang G S, et al. Progress on design and R&D for helium-cooled ceramic breeder TBM in China. Fusion Eng Des, 2012, 87(7-8): 1138 doi: 10.1016/j.fusengdes.2012.02.098
[12]	Kawamura H, Takahashi H, Yoshida N, et al. Application of beryllium intermetallic compounds to neutron multiplier of fusion blanket. Fusion Eng Des, 2002, 61-62: 391 doi: 10.1016/S0920-3796(02)00106-0
[13]	Kurinskiy P, Moeslang A, Chakin V, et al. Characteristics of microstructure, swelling and mechanical behaviour of titanium beryllide samples after high-dose neutron irradiation at 740 and 873 K. Fusion Eng Des, 2013, 88(9-10): 2198 doi: 10.1016/j.fusengdes.2013.05.084
[14]	Nakamichi M, Kim J H. Homogenization treatment to stabilize the compositional structure of beryllide pebbles. J Nucl Mater, 2013, 440(1-3): 530 doi: 10.1016/j.jnucmat.2013.02.070
[15]	Nakamichi M, Kim J H. Fabrication and hydrogen generation reaction with water vapor of prototypic pebbles of binary beryllides as advanced neutron multiplier. Fusion Eng Des, 2015, 98-99: 1838 doi: 10.1016/j.fusengdes.2015.04.026
[16]	Kim J H, Nakamichi M. Optimization of synthesis conditions for plasma-sintered beryllium–titanium intermetallic compounds. J Alloys Compd, 2013, 577: 90 doi: 10.1016/j.jallcom.2013.04.185
[17]	Nakamichi M, Kim J H, Munakata K, et al. Preliminary characterization of plasma-sintered beryllides as advanced neutron multipliers. J Nucl Mater, 2013, 442(1-3, Suppl 1): S465 doi: 10.1016/j.jnucmat.2012.11.011
[18]	Liu P P, Zhan Q, Fu Z Y, et al. Surface and internal microstructure damage of He–ion–irradiated CLAM steel studied by cross-sectional transmission electron microscopy. J Alloys Compd, 2015, 649: 859 doi: 10.1016/j.jallcom.2015.07.177
[19]	Zhang C H, Chen K Q, Wang Y S, et al. Formation of bubbles in helium implanted 316L stainless steel at temperatures between 25 and 550 °C. J Nucl Mater, 1997, 245(2-3): 210 doi: 10.1016/S0022-3115(97)00007-X
[20]	Zhang C H, Chen K Q, Wang Y S, et al. The formation of helium bubbles in 316L stainless steel irradiated with 2.5 MeV He⁺ ions. Acta Phys Sin, 1997, 46(9): 1774 doi: 10.3321/j.issn:1000-3290.1997.09.017 張崇宏, 陳克勤, 王引書, 等. 2.5 MeV的He⁺離子輻照316L不銹鋼中氦泡的形核與生長研究. 物理學報, 1997, 46(9):1774 doi: 10.3321/j.issn:1000-3290.1997.09.017
[21]	Trinkaus H. Modeling of helium effects in metals: high temperature embrittlement. J Nucl Mater, 1985, 133: 105
[22]	Trinkaus H. On the modeling of the high-temperature embrittlement of metals containing helium. J Nucl Mater, 1983, 118(1): 39 doi: 10.1016/0022-3115(83)90177-0
[23]	Li X C, Liu Y N, Yu Y, et al. Helium defects interactions and mechanism of helium bubble growth in tungsten: a molecular dynamics simulation. J Nucl Mater, 2014, 451(1-3): 356 doi: 10.1016/j.jnucmat.2014.04.022
[24]	Trinkaus H, Singh B N. Helium accumulation in metals during irradiation: where do we stand? J Nucl Mater, 2003, 323(2-3): 229 doi: 10.1016/j.jnucmat.2003.09.001
[25]	Fu C C, Willaime F. Ab initio study of helium in α-Fe: dissolution, migration, and clustering with vacancies. Phys Rev B, 2005, 72(6): 064117 doi: 10.1103/PhysRevB.72.064117
[26]	Evans J H. An interbubble fracture mechanism of blister formation on helium-irradiated metals. J Nucl Mater, 1977, 68(2): 129 doi: 10.1016/0022-3115(77)90232-X
[27]	Gusev V M, Guseva M I, Martynenko Y V, et al. Helium blistering at high irradiation doses. J Nucl Mater, 1979, 85-86: 1101 doi: 10.1016/0022-3115(79)90407-0
[28]	Liu Y Z, Li B S, Zhang L. High-temperature annealing induced He bubble evolution in low energy He ion implanted 6H–SiC. Chin Phys Lett, 2017, 34(5): 052801 doi: 10.1088/0256-307X/34/5/052801
[29]	Daghbouj N, Li B S, Karlik M, et al. 6H–SiC blistering efficiency as a function of the hydrogen implantation fluence. Appl Surf Sci, 2019, 466: 141 doi: 10.1016/j.apsusc.2018.10.005