铝合金材料在14 MeV中子

李余; 张晓民; 程胜寒; 杨阳; 陈志林; 彭太平

doi:10.11884/HPLPB201931.180222

铝合金材料在14 MeV中子

doi: 10.11884/HPLPB201931.180222

1.
中国工程物理研究院核物理与化学研究所，四川绵阳 621900
2.
海军 91049 部队，山东青岛 266000

详细信息

作者简介:
李余(1991—), 女，博士研究生，从事聚变装置辐射防护技术研究；liyu0904@caep.cn

通讯作者:
陈志林(1984—), 男，副研究员，长期从事氚分析测量、聚变装置辐射防护技术研究；chenzhilin@caep.cn

中图分类号: TL7
计量
- 文章访问数: 1250
- HTML全文浏览量: 296
- PDF下载量: 72
- 被引次数: 0
出版历程
- 收稿日期: 2018-08-17
- 修回日期: 2019-01-30
- 刊出日期: 2019-02-15

Analysis of activation characteristics of aluminum alloy irradiated by 14 MeV neutrons

1.
Institute of Nuclear Physics and Chemistry, CAEP, Mianyang 621900, China
2.
Navy 91049 Unite, Qingdao 266000, China

摘要

摘要: 铝合金是激光惯性约束聚变(ICF)装置中最常用的结构材料之一，将直接受到高能量、高产额的中子辐照。评估铝合金材料在14 MeV中子辐照下的活化特性，可为我国ICF装置的材料选取提供参考。采用FISPACT活化计算软件，计算并比较了三种不同牌号的铝合金材料在14 MeV中子辐照后产生的比活度和剂量率，并分析了不同元素对比活度和剂量率的贡献。结果表明，铝合金的比活度和剂量率在冷却一周之内下降了3个数量级。铝合金的活化主要来自Al元素、Mn元素和Zn元素，主要活化产物为²⁴Na, ⁵⁴Mn和⁶⁵Zn。Al元素在冷却一周内对比活度(剂量率)的贡献大于90%，其余两种元素在两周之后占主导作用，其贡献之和超过50%。通过选取低Mn, Zn质量分数的铝合金，可降低材料在活化后的放射性水平。
- 聚变中子 /
- 铝合金 /
- 活化 /
- 活度 /
- 剂量 /
- 辐射防护
Abstract: Aluminum alloy, as a kind of important structural materials used in laser-driven Inertial Confinement Fusion (ICF) facilities, will be exposed to high-energy neutrons with high yields. The activation level of aluminum alloys should be taken into account when selecting the materials used in ICF facilities during design. Specific activities and dose rates for three different aluminum alloys after irradiation by 14 MeV neutrons were calculated and compared using the FISPACT inventory code. The results show that both specific activity and dose rate decrease 3 magnitudes in one week after irradiation. It is found that aluminum contributes to more than 90% of the total activity (dose rate) in the first week while Manganese and zinc in aluminum alloys are dominant in longer cooling times. The main residual nuclides are ²⁴Na, ⁵⁴Mn and ⁶⁵Zn.For safety considerations, it is better to choose aluminum alloys with lower Mn and Zn contents.
- fusion neutron /
- aluminum alloy /
- activation /
- activity /
- dose /
- radiation protection

HTML全文

图 1 材料活化后比活度随时间变化

Figure 1. Specific activity as a function of time after activation

下载: 全尺寸图片幻灯片

图 2 材料活化后剂量率随时间变化

Figure 2. Dose rate as a function of time after activation

下载: 全尺寸图片幻灯片

图 3 不同元素对5083比活度和剂量率的贡献

Figure 3. Contribution of different elements to specific activity and dose rate for 5083

下载: 全尺寸图片幻灯片

图 4 不同元素对6061比活度和剂量率的贡献

Figure 4. Contribution of different elements to specific activity and dose rate for 6061

下载: 全尺寸图片幻灯片

图 5 不同元素对7075比活度和剂量率的贡献

Figure 5. Contribution of different elements to specific activity and dose rate for7075

下载: 全尺寸图片幻灯片

图 6 元素活化后比活度和剂量率随时间变化

Figure 6. Specific activity and dose rate as a function of time after activation

下载: 全尺寸图片幻灯片

表 1 铝合金材料各成分质量分数

Table 1. Chemical composition of aluminium alloys

material number	mass fraction/%
material number	Fe	Mn	Si	Cr	Al	Cu	Mg	Zn	Ti
7075	0.50	0.60	0.40	0.28	89.62	1.20	2.10	5.10	0.20
6061	0.70	0.15	0.80	0.35	96.65	0.15	0.80	0.25	0.15
5083	0.40	1.00	0.40	0.25	93.55	0.10	4.00	0.20	0.10

下载: 导出CSV

表 2 主要活化产物信息

Table 2. The main radioactive products

radionuclide	T_1/2	decay mode	gamma energy/keV	main reaction channel	cross section at E_n=14 MeV/barn
²⁴Na	14.997 h	Beta-	1368.626(99.9936) 2754.007(99.855)	²⁷Al(n, α)²⁴Na ²⁴Mg(n, p)²⁴Na	0.12 0.19
⁵¹Cr	27.701 d	E.C.	320.0824(9.910)	⁵²Cr(n, 2n) ⁵¹Cr	0.26
⁵⁵Fe	2.733 y	E.C.	—	⁵⁶Fe(n, 2n) ⁵⁵Fe	0.41
⁵⁴Mn	312.05 d	E.C.	834.848(99.9760)	⁵⁵Mn(n, 2n) ⁵⁴Mn	0.78
⁶⁵Zn	243.93 d	Beta+/E.C.	1115.539(50.04)	⁶⁶Zn (n, 2n) ⁶⁵Zn	0.60

下载: 导出CSV

参考文献(9)

[1]	Moses E I. The National Ignition Facility and the National Ignition Campaign[J]. IEEE Trans Plasma Science, 2010, 38(4): 684-689. doi: 10.1109/TPS.2010.2042466
[2]	Brereton S. Overview of the National Ignition Facility[J]. Health Physics, 2013, 104(6): 544-556. doi: 10.1097/HP.0b013e31828cf5cd
[3]	Foley R J, Karpenko V P, Adams C H, et al. Design of the target area for the National Ignition Facility[C] //The 2nd Annual International Conference on Solid State Lasers for Application to ICF, 1996.
[4]	Latkowski J F, Tobin M T, Singh M S. Neutronics and shielding analysis of the National Ignition Facility[C] //The 11th Topical Meeting on the Technology of Fusion Energy. 1994.
[5]	Sitaraman S, Brereton S, Dauffy L, et al. Post-shot radiation environment following low-yield shots inside the National Ignition Facility[R]. LLNL-CONF-461492, 2010.
[6]	GB/T 3190—2008, 变形铝及铝合金化学成分[S]. GB/T 3190-2008. Wrought aluminum and aluminum alloy-chemical components
[7]	Forrest R A. FISPACT-2007: user manual[R]. Report UKAEA FUS 534, 2007.
[8]	Forrest R A, Kopecky J. The activation system EASY-2007[J]. Journal of Nuclear Materials, 2009, 386-388: 878-881. doi: 10.1016/j.jnucmat.2008.12.194
[9]	Sidell J. EXTRA: A digital computer program for the solution of stiff sets of ordinary initial value, first order differential equations[R]. AEEW-R-799, 1976.