Calculation of radiation damage of key components of China Spallation Neutron Source II target station

Cao Song; Yin Wen; Zhou Bin; Hu Zhi-Liang; Shen Fei; Yi Tian-Cheng; Wang Song-Lin; Liang Tian-Jiao

doi:10.7498/aps.73.20240088

Abstract

China Spallation Neutron Source (CSNS) I project passed the national acceptance in 2018, and current beam power has reached 140 kW. In order to further improve the output neutron strength of the target station moderator, a 500 kW power upgrade plan has been proposed for CSNS II. The target station is an important part of the spallation neutron source. In the target station, a large number of neutrons are produced by the spallation reaction between high energy protons and the target, these neutrons are moderated by the moderator and become neutrons for neutron scattering experiments. During operation, the target and other key components such as the target container, the moderator reflector container, and the proton beam window are irradiated by high-flux and high-energy particles for a long time, which will result in serious radiation damage. It is important to assess the accumulated radiation damage during operation to determine the service life of each component. At present, the physical quantities used to evaluate the radiation damage degree of materials include displacement per atom (DPA), H and He production. In this work, the displacement damage cross sections of protons and neutrons and the H, He production cross sections for W, SS316 and Al-6061 materials are obtained by using PHITS. The effects of the Norgett-Robinson-Torrens (NRT) model and athermal recombination corrected (ARC) model on the calculation of displacement damage are analyzed. The results show that the cross section calculated based on ARC model is lower than that based on NRT model, because the NRT model does not take into account the resetting of the atoms before reaching thermodynamic equilibrium. On this basis, DPA, H and He production of the key components of the target station operating for 5000 h at a power of 500 kW are calculated by combining the baseline model of the second phase target station of the spallation neutron source in China. The results show that the yields of NRT-dpa, ARC-dpa, H and He produced by irradiation are 8.01 dpa/y (in this paper, 1 y = 2500 MW·h), 2.39 dpa/y, 5110 appm/y and 884 appm/y, respectively. The radiation damage values of the target vessel are 5.34 dpa/y, 1.92 dpa/y, 2180 appm/y and 334 appm/y, respectively. The radiation damage values of the moderators and reflectors are 3.78 dpa/y, 1.77 dpa/y, 124 appm/y, and 36.7 appm/y. The radiation damage values of the proton beam window are 0.35 dpa/y, 0.19 dpa/y, 962 appm/y, and 216 appm/y. Subsequently, the life of each component is estimated by analyzing the radiation damage. These results are very important for analyzing the radiation damage of these parts, and constructing reasonable maintenance programs.

Keywords:

target station of China Spallation Neutron Source II /
radiation damage /
ARC-dpa /
PHITS simulation

Authors and contacts

1.
Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049, China
2.
School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing 100049, China
3.
Guangdong-Hong Kong-Macao Joint Laboratory of Neutron Scattering Science and Technology, Dongguan 523800, China

Corresponding author: Wang Song-Lin, wangsl@ihep.ac.cn ; Liang Tian-Jiao, liangtj@ihep.ac.cn

Funds: Project supported by the Joint Funds of the National Natural Science Foundation of China (Grant No. U1932219), the Program for Guangdong Introducing Innovative and Entrepreneurial Teams, China (Grant No. 2017ZT07S225), and the Mobility Programme endorsed by the Joint Committee of the Sino-German Center, China (Grant No. M-0728).

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References

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[2]	于全芝, 殷雯, 梁天骄 2011 物理学报 60 052501 Google Scholar Yu Q Z, Yin W, Liang T J 2011 Acta Phys. Sin. 60 052501 Google Scholar
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[5]	Norgett M J, Robinson M T, Torrens I M 1975 Nucl. Engs. Des. 33 50 Google Scholar
[6]	Broeders C H M, Konobeyev A Yu 2005 J. Nucl. Mater. 336 201 Google Scholar
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[19]	Konobeyev A Yu, Fischer U, Korovin Y A 2017 Nucl. Eng. Technol. 3 169 Google Scholar
[20]	Yin W, Konobeyev A Yu, Leichtle D, Cao L Z 2023 J. Nucl. Mater. 573 154143 Google Scholar
[21]	Lindhard J, Nielsen V, Scharff M 1968 Mat. Fys. Medd. Dan. Vid. Selsk. 36 3
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[23]	Burke E A 1986 IEEE T. Nucl. Sci. 33 1276 Google Scholar
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Cited By

图 1 CSNS靶站的TMR结构示意图

Figure 1. Structural diagram of TMR of CSNS target station.

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图 2 弹性散射和非弹性散射对W的质子离位损伤截面的贡献

Figure 2. Contribution of elastic scattering and inelastic scattering to the proton displacement cross section of W.

DownLoad: Full-Size Img PowerPoint

图 3 W, SS316, Al-6061的离位损伤截面　(a) p+W; (b) n+W; (c) p+SS316; (d) n+SS316; (e) p+Al-6061; (f) n+Al-6061

Figure 3. Displacement cross section of W, SS316, Al-6061: (a) p+W; (b) n+W; (c) p+SS316; (d) n+SS316; (e) p+Al-6061; (f) n+Al-6061.

DownLoad: Full-Size Img PowerPoint

图 4 W, SS316, Al-6061的H, He产生截面　(a) W-H; (b) W-He; (c) SS316-H; (d) SS316-He; (e) Al-6061-H; (f) Al-6061-He

Figure 4. H, He production cross section of W, SS316, Al-6061: (a) W-H; (b) W-He; (c) SS316-H; (d) SS316-He; (e) Al-6061-H; (f) Al-6061-He.

DownLoad: Full-Size Img PowerPoint

图 5 靶站几何模型　(a) TMR系统y-z轴截面图, 其中+y为质子入射方向; (b)质子束窗

Figure 5. Geometric model of target station: (a) Plane diagram of the y-z axis of the TMR system, where +y is the proton incident direction; (b) proton beam window.

DownLoad: Full-Size Img PowerPoint

图 6 靶站入射质子束斑形状

Figure 6. Shape of the incident proton beam at the target station.

DownLoad: Full-Size Img PowerPoint

图 7 靶、靶容器和慢化器反射体容器的质子和中子通量

Figure 7. Proton and neutron fluxes of targets, target containers, and moderator reflector containers.

DownLoad: Full-Size Img PowerPoint

图 8 靶体ARC-dpa的空间分布(x-y平面)　(a) p+ARC-dpa; (b) n+ARC-dpa; (c) total+ARC-dpa

Figure 8. ARC-dpa spatial distribution of target (x-y plane): (a) p+ARC-dpa; (b) n+ARC-dpa; (c) total+ARC-dpa.

DownLoad: Full-Size Img PowerPoint

图 9 靶体DPA在y (质子入射)方向的分布

Figure 9. DPA distribution of target in the y (proton incidence) direction.

DownLoad: Full-Size Img PowerPoint

图 10 靶窗ARC-dpa的空间分布(x-z平面)　(a) p+ARC-dpa; (b) n+ARC-dpa

Figure 10. ARC-dpa spatial distribution of target window (x-z plane): (a) p+ARC-dpa; (b) n+ARC-dpa.

DownLoad: Full-Size Img PowerPoint

图 11 CHM容器靠近靶体位置He产额分布(x-y平面)　(a)质子; (b)中子

Figure 11. He production spatial distribution of CHM vessel: (a) Proton; (b) neutron.

DownLoad: Full-Size Img PowerPoint

表 1 SS316不锈钢、6061铝合金的核素组成

Table 1. Nuclide composition of SS316 stainless steel and 6061 aluminum alloy.

材料	核素原子数百分比
SS316	Fe (65.4%), Cr (17.0%), Ni (12.0%), Mo (2.5%) Mn (2%), Si (1%), P (0.045%), C (0.03%)
Al-6061	Al (98.2%), Mg (1.1%), Si (0.0057%)

DownLoad: CSV

表 2 部分元素的E_d, b_arc, c_arc参数值

Table 2. The E_d, b_arc, c_arc values of some elements.

元素	E_d/eV	b_arc	c_arc
Mg	20	–1.00	0.45
Al	27	–0.82	0.44
Cr	40	–1.01	0.37
Fe	40	–0.57	0.29
Ni	39	–1.01	0.23
Mn	32.5	–1.00	0.33
W	70	–0.55	-0.25

DownLoad: CSV

表 3 质子束窗辐照损伤最大值

Table 3. Maximum radiation damage value of proton beam window.

	Proton	Neutron	Total
NRT-dpa/(dpa·y^–1)	0.34	0.0069	0.35
ARC-dpa/(dpa·y^–1)	0.18	0.0044	0.19
比值/(NRT/ARC)	1.87	1.57	1.86
H 产额/(appm·y^–1)	961	0.61	962
He 产额/(appm·y^–1)	216	0.19	216

DownLoad: CSV

表 4 W, SS316, Al-6061的辐照损伤限值

Table 4. Radiation damage limit of W, SS316, Al-6061.

材料	NRT-dpa 限值/dpa	ARC-dpa 限值/dpa	He产额限值/appm
W	10	3.0
SS316	12	4.3
Al-6061	40	18.7	2000

DownLoad: CSV

表 5 靶站关键部件的辐照损伤值和预期寿命

Table 5. Radiation damage value and lifetime of key components of target station.

部件	材料	NRT-dpa/(dpa·y^–1)	ARC-dpa/(dpa·y^–1)	H产额/(appm·y^–1)	He产额/(appm·y^–1)	寿命/year
靶体	W	8.01	2.39	5110	884	1.25
靶容器	SS316	5.34	1.92	2180	334	2.25
慢化器容器	Al-6061	3.78	1.77	124	36.7	10.5
质子束窗	Al-6061	0.348	0.187	962	216	9.26

DownLoad: CSV

[1]	Wei J, Fu S N, Tang J Y, Tao J Z, Wang D S, Wang F W, Wang S 2009 Chin. Phys. C 33 1033 Google Scholar
[2]	于全芝, 殷雯, 梁天骄 2011 物理学报 60 052501 Google Scholar Yu Q Z, Yin W, Liang T J 2011 Acta Phys. Sin. 60 052501 Google Scholar
[3]	Yin W, Yu Q Z, Lu Y L, Wang S L, Tong J F, Liang T J 2012 J. Nucl. Mater. 431 39 Google Scholar
[4]	Simon G W, Denney J M, Downing R G 1963 Phys. Rev. 129 2454 Google Scholar
[5]	Norgett M J, Robinson M T, Torrens I M 1975 Nucl. Engs. Des. 33 50 Google Scholar
[6]	Broeders C H M, Konobeyev A Yu 2005 J. Nucl. Mater. 336 201 Google Scholar
[7]	Broeders C H M, Konobeyev A Yu, Villagrasa C 2005 J. Nucl. Mater. 342 68 Google Scholar
[8]	Konobeyev A Yu, Broeders C H M, Fischer U 2007 Proceedings of the 8th International Topical Meeting on the Nuclear Applications of Accelerator Technology (AccApp’07) Pocatello, Idaho, July 29–August 2, 2007 p241
[9]	Konobeyev A Yu, Fischer U 2014 Proceedings of the HB 2014 East-Lansing, MI, USA, November 10–14, 2014 pTHO4AB02
[10]	Nordlund K, Zinkle S J, Sand A E, Granberg F, Averback R S, Stoller R, Suzudo T, Malerba L, Banhart F, Weber W J, Willaime F, Dudarev S L, Simeone D 2018 Nat. Common. 9 1084 Google Scholar
[11]	Konobeyev A Yu, Fischer U, Simakov S P 2018 Nucl. Instrum. Methods Phys. Res., Sect. B 431 55 Google Scholar
[12]	Konobeyev A Yu, Fischer U, Simakov S P 2019 Nucl. Eng. Technol. 51 170 Google Scholar
[13]	Herbach C M, Hilscher D, Jahnke U, Tishchenko V G, Galin J, Letourneau A, Péghaire A, Filges D, Goldenbaum F, Pienkowski L, Schröder W U, Tõke J 2006 Nucl. Phys. A 765 426 Google Scholar
[14]	Barnett M H, Wechsler M S, Dudziak D J, Mansur L K, Murphy B D 2001 J. Nucl. Mater. 296 54 Google Scholar
[15]	Lu W, Wechsler M S, Dai Y 2003 J. Nucl. Mater. 318 176 Google Scholar
[16]	Meigo S, Ooi M, Harada M, Kinoshita H, Akutsu A 2014 J. Nucl. Mater. 450 141 Google Scholar
[17]	Koning A J, Rochman D, Sublet J C, Dzysiuk N, Fleming M, Marck S 2019 Nucl. Data Sheets 155 1 Google Scholar
[18]	Sato T, Iwamoto Y, Hashimoto S, Ogawa T, Furuta T, Abe S, Kai T, Tsai P, Matsuda N, Iwase H, Shigyo N, Sihver L, Niita K 2018 J. Nucl. Sci. Technol. 55 684 Google Scholar
[19]	Konobeyev A Yu, Fischer U, Korovin Y A 2017 Nucl. Eng. Technol. 3 169 Google Scholar
[20]	Yin W, Konobeyev A Yu, Leichtle D, Cao L Z 2023 J. Nucl. Mater. 573 154143 Google Scholar
[21]	Lindhard J, Nielsen V, Scharff M 1968 Mat. Fys. Medd. Dan. Vid. Selsk. 36 3
[22]	Jun I 2001 IEEE T. Nucl. Sci. 48 162 Google Scholar
[23]	Burke E A 1986 IEEE T. Nucl. Sci. 33 1276 Google Scholar
[24]	Boudard A, Cugnon J, David J C, Leray S, Mancusi D 2013 Phys. Rev. C 87 014606 Google Scholar
[25]	Niita K 1995 Phys. Rev. C 52 2620 Google Scholar
[26]	Furihata S 2000 Nucl. Instrum. Methods Phys. Res. B 171 251 Google Scholar
[27]	Jung P 1983 J. Nucl. Mater. 117 70 Google Scholar
[28]	Iwamoto Y, Yoshida M, Matsuda H, Meigo S, Satoh D, Yashima H, Yabuuchi A, Shima T 2021 Mater. Sci. Forum. 1024 95 Google Scholar
[29]	Iwamoto Y, Yoshida M, Matsuda H, Meigo S, Satoh D, Yashima H, Yabuuchi A, Shima T 2020 JPS Conf. Proc. 28 061003 Google Scholar
[30]	Greene G A, Snead C L, Finfrock C C, Hanson A L, James M R, Sommer W F, Pitcher E J, Waters L S 2003 Proceedings of the 6th International Meeting on Nuclear Applications of Accelerator Technology (AccApp’03) San Diego, USA, June 1–5, 2003 pp881–892
[31]	Dai Y, Foucher Y, James M R, Oliver B M 2003 J. Nucl. Mater. 318 167 Google Scholar
[32]	Chen J, Ullmaier H, Floβdorf T, Kuhnlein W, Duwe R, Carsughi F, Broome T 2001 J. Nucl. Mater. 298 248 Google Scholar
[33]	Oak Ridge National Laboratory 2020 Spallation neutron Source Second Target Station Conceptual Design Report Volume 1: Overview, Technical experimental system S01010000-TR0001, R00
[34]	Iwamoto Y, Meigo S, Hashimoto S 2020 J. Nucl. Mater. 538 1522 Google Scholar

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