Numerical simulation method and application study on deuteron ion and fusion neutron coupling transportation
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摘要: 对加速器驱动中子发生器的数值模拟包括离子输运、聚变反应、中子输运等。由于核反应截面远低于带电粒子输运的库仑截面，且核反应平均自由程远大于靶厚度，直接蒙卡抽样难以抽到聚变反应。在MCNPX程序基础上，采用“强迫”聚变方法，即每个入射氘核必发生一次聚变反应，聚变反应处氘核的真实状态(位置、能量和方向)以抽样产生，并以此状态来确定聚变中子的出射状态，实现了氘核与聚变中子的耦合输运模拟计算。研究结果表明，该方法能够给出氘核输运对聚变中子能谱和角分布的影响，中子产额计算结果符合预期。Abstract: Deuteron ion transportation, fusion reaction sampling and neutron transportation simulation are included in the numerical calculation of accelerator driven neutron generator. As well known, the nuclear reaction cross section is much smaller than Coulomb cross section of charged particle transportation, and the mean free path of nuclear reaction is far longer than the depth of target, compared to deuteron ion transportation, the direct sampling efficiency of fusion reaction is almost zero. In this paper, a "forced" fusion arithmetic is introduced and embedded into MCNPX program. By the "forced" fusion arithmetic, fusion reaction must happen for every source deuteron ion. The position, energy and flight direction of deuteron ion that interact with tritium are sampled from all energy steps. The position, energy and flight direction of fusion source neutron are sampled according to that of deuteron ion. The deuteron ion and neutron coupling transportation can be calculated with the revised MCNPX.
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Key words:
- neutron generator /
- yield /
- energy spectrum /
- angular distribution /
- stochastic simulation
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图 2 中子产额以及与文献[6]的相对偏差
Figure 2. Comparison of neutron yield curves and relative difference value curves
表 1 聚变中子平均能量
Table 1. Average energy of fusion neutrons
Ed0/MeV 0.1 0.2 0.30 0.4 0.5 0.6 0.99 En/MeV 14.113 14.139 14.158 14.171 14.183 14.197 14.25 
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[1] 苏桐龄. 强流中子发生器及其应用[J]. 核技术, 1989, 12 (8/9): 553-556. https://www.cnki.com.cn/Article/CJFDTOTAL-HJSU1989Z1023.htmSu Tongling. Intense neutron generator and its applications. Nuclear Techniques, 1989, 12 (8/9): 553-556 https://www.cnki.com.cn/Article/CJFDTOTAL-HJSU1989Z1023.htm [2] Koivunoro H, Bleuel D L, Nastasi U, et al. BNCT dose distribution in liver with epithermal D-D and D-T fusion-based neutron beams[J]. Applied Radiation and Isotopes, 2004, 61 : 853-859. doi: 10.1016/j.apradiso.2004.05.043 [3] Verbeke J M, Leung K N, Vujic J. Development of a sealed accelerator tube neutron generator[J]. Applied Radiation and Isotopes, 2000, 53 : 801-809. doi: 10.1016/S0969-8043(00)00262-1 [4] 石磊, 唐平瀛, 谈效华. d-T和d-D中子产额的可视化计算[J]. 原子能科学技术, 2004, 38 (s): 83-88. https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2004S1022.htmShi Lei, Tang Pingying, Tan Xiaohua. Visual computation for d-T and d-D neutron yield. Atomic Energy Science and Technology, 2004, 38 (s): 83-88 https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2004S1022.htm [5] 姚泽恩, 岳伟明, 罗鹏, 等. 厚靶T(d, n)4He反应加速器中子源的中子产额、能谱和角分布[J]. 原子能科学技术, 2008, 42 (5): 400-403. https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS200805004.htmYao Ze'en, Yue Weiming, Luo Peng, et al. Neutron yield, energy spectrum and angular distribution of accelerator based T(d, n)4He reaction neutron source for thick target. Atomic Energy Science and Technology, 2008, 42 (5): 400-403 https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS200805004.htm [6] 岳伟明, 姚泽恩. D-T中子发生器中子产额、能谱、角分布及中子伽玛混合场的模拟研究[D]. 兰州: 兰州大学, 2008.Yue Weiming, Yao Ze'en. Study on the Neutron yield, energy spectrum, angular distribution and neutron/gamma mixed field of D-T neutron generator using Monte Carlo method. Lanzhou: Lanzhou University, 2008 [7] Jamse F Z. SRIM-2003[J]. Nuclear Instruments and Methods in Physics Research, 2004, B219/220 : 1027-1036. [8] Pelowitz D B. MCNPX User's Manual, Version 2.6.0[R]. LA-CP-07-1473, 2008. [9] 卢希庭. 原子核物理[M]. 北京: 原子能出版, 2000.Lu Xiting. Nuclear physics. Beijing: Atomic Energy Press, 2000 [10] Horst L, Arno P. Neutron production cross section and energies for the reactions T(p, n)3He, D(d. n)3He and T(d, n)4He[J]. Nuclear Data Tables, 1973, 11 : 569-619. doi: 10.1016/S0092-640X(73)80081-6 -
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