Research on radiation protection factors of basic ship structures
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摘要: 核辐射环境中,舰船、坦克的辐射屏蔽特性关乎着核安全、防护、效应评估以及决策应对等实际应用问题。瞄准舰船的核辐射屏蔽性能开展研究。针对舰船材料及典型结构,采用中子-光子耦合输运方法,定量给出中子源、γ源同时辐照下的辐射屏蔽效能。通过借助大规模并行技术,实现了该深穿透屏蔽问题的高效模拟。该辐照屏蔽研究中考虑了入射中子和γ以及次级γ粒子的综合叠加效应。通过模拟中子和γ分别入射不同厚度、不同材料壳体后的注量、剂量、能谱演化,计算获得了屏蔽体的入射中子、入射γ射线、中子和次级γ及其综合屏蔽因子,给出腔内的屏蔽因子分布规律,材料包括Fe、Al、Pb、船体材料HSLA100钢等,辐射源包括单能中子、单能γ以及核泄漏中子谱和γ谱。研究成果将为船体、坦克等的辐射防护性能的深入分析奠定基础,为核辐射效应评估、应急处理等提供理论支撑。Abstract: In nuclear radiation environment, the radiation protection of vehicles such as ships and tanks is crucial for nuclear safety, radiation protection, radiation damage assessment, response and decision-making. This paper does research on ships’ radiation shielding performance. Using ship materials and typical structures, neutron-photon coupling transportation method is adopted to quantitatively simulate ship’s radiation shielding performance, under neutron and γ’ simultaneous irradiation. By utilizing large-scale parallel technology, efficient simulation has been achieved for deep-penetrating problem. The simulation of radiation transportation process considers incident neutrons, γ and even secondary particles. For basic shape models such as plate, cavity with different thicknesses and materials, it simulates neutron and γ's transportation in gas and materials, monitors particles flux, dose, and energy spectrum. The radiation protection factors(RPF) for neutrons, γ rays, and both are simulated and analyzed. It studies RPF influence rules with key parameter such as plate thicknesses, incident angles. The materials researched include Fe, Al, Pb, HSLA100 steel, and the radiation sources include single energy neutron, and nuclear leaked neutron and γ spectra. These results will contribute to the analysis of vehicles’ radiation protection performance, and provide theoretical support for nuclear radiation effect assessment, emergency response, etc.
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Key words:
- neutron /
- gamma /
- radiation protection factor /
- ship materials /
- cavity /
- plate
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表 1 HSLA-100钢的化学成分
Table 1. Chemical composition of HSLA-100 steel
element mass fraction/% C 0.026 Mn 1.520 P 0.002 S 0.001 Si 0.280 Ni 2.710 Cr 0.040 Mo 0.480 Cu 0.075 Al 0.002 Ti 0.005 O 0.018 N 0.003 Fe 94.878 -
[1] Leung J K C. Application of shielding factors for protection against gamma radiations during a nuclear accident[J]. IEEE Transactions on Nuclear Science, 1992, 39(5): 1512-1518. doi: 10.1109/23.173235 [2] Singh V P, Badiger N M. Investigation on radiation shielding parameters of ordinary, heavy and super heavy concretes[J]. Nuclear Technology and Radiation Protection, 2014, 29(2): 149-156. doi: 10.2298/NTRP1402149S [3] Dickson E D, Hamby D M. Experimental shielding evaluation of the radiation protection provided by the structurally significant components of residential structures[J]. Journal of Radiological Protection, 2014, 34(1): 201-221. doi: 10.1088/0952-4746/34/1/201 [4] Singh V P, Medhat M E, Badiger N M. Assessment of exposure buildup factors of some oxide dispersion strengthened steels applied in modern nuclear engineering and designs[J]. Nuclear Engineering and Design, 2014, 270: 90-100. doi: 10.1016/j.nucengdes.2013.12.046 [5] Singh V P, Medhat M E, Badiger N M, et al. Radiation shielding effectiveness of newly developed superconductors[J]. Radiation Physics and Chemistry, 2015, 106: 175-183. doi: 10.1016/j.radphyschem.2014.07.013 [6] Singh V P, Badiger N M. Comprehensive study on energy absorption buildup factors and exposure buildup factors for photon energy 0.015 to 15 MeV up to 40 mfp penetration depth for gel dosimeters[J]. Radiation Physics and Chemistry, 2014, 103: 234-242. doi: 10.1016/j.radphyschem.2014.05.033 [7] Singh V P, Badiger N M, Kothan S, et al. Gamma-ray and neutron shielding efficiency of Pb-free gadolinium-based glasses[J]. Nuclear Science and Techniques, 2016, 27: 103. doi: 10.1007/s41365-016-0099-1 [8] Cherkashina N I, Pavlenko V I, Shkaplerov A N, et al. Neutron attenuation in some polymer composite material[J]. Advances in Space Research, 2024, 73(5): 2638-2651. doi: 10.1016/j.asr.2023.12.003 [9] Singh P S, Singh T, Kaur P. Variation of energy absorption buildup factors with incident photon energy and penetration depth for some commonly used solvents[J]. Annals of Nuclear Energy, 2008, 35(6): 1093-1097. doi: 10.1016/j.anucene.2007.10.007 [10] Akar Tarim U, Gurler O, Ozmutlu E N, et al. Monte Carlo calculations for gamma-ray mass attenuation coefficients of some soil samples[J]. Annals of Nuclear Energy, 2013, 58: 198-201. doi: 10.1016/j.anucene.2013.03.021 [11] 邓力. 输运问题蒙特卡罗模拟方法回顾及展望[J]. 强激光与粒子束, 2022, 34:026001 doi: 10.11884/HPLPB202234.210402Deng Li. Retrospect and outlook of Monte Carlo simulated methods for transport problems[J]. High Power Laser and Particle Beams, 2022, 34: 026001 doi: 10.11884/HPLPB202234.210402 [12] 柴辰睿, 郝建红, 张芳, 等. 舰船舱室的早期伽马辐射屏蔽特性[J]. 强激光与粒子束, 2024, 36:043029 doi: 10.11884/HPLPB202436.230373Chai Chenrui, Hao Jianhong, Zhang Fang, et al. Shielding characteristics of ship cabin against early gamma radiation in nuclear explosions[J]. High Power Laser and Particle Beams, 2024, 36: 043029 doi: 10.11884/HPLPB202436.230373 [13] 郑建华, 晏骥, 苏明, 等. 神光Ⅲ主机装置内爆中子和伽马辐射特性的数值模拟[J]. 强激光与粒子束, 2015, 27:112007 doi: 10.11884/HPLPB201527.112007Zheng Jianhua, Yan Ji, Su Ming, et al. Numerical study on characteristics of neutron and gamma radiations from implosions on Shenguang Ⅲ laser facility[J]. High Power Laser and Particle Beams, 2015, 27: 112007 doi: 10.11884/HPLPB201527.112007 [14] Cho G, Kim H K, Woo H, et al. Electronic dose conversion technique using a NaI(Tl) detector for assessment of exposure dose rate from environmental radiation[J]. IEEE Transactions on Nuclear Science, 1998, 45(3): 981-985. doi: 10.1109/23.682692 [15] 谭笑, 邓力, 张玲玉, 等. JMCT3.0蒙特卡罗质子及低能光子/电子输运功能开发及检验[J]. 强激光与粒子束, 2024, 36:096002 doi: 10.11884/HPLPB202436.240117Tan Xiao, Deng Li, Zhang Lingyu, et al. Development and tests of functions of proton, low-energy photon and electron transport in JMCT3.0 Monte Carlo particle transport program[J]. High Power Laser and Particle Beams, 2024, 36: 096002 doi: 10.11884/HPLPB202436.240117 [16] 申靖文, 胡也, 郑俞, 等. 蒙特卡罗输运模拟软件JMCT的深穿透屏蔽计算[J]. 强激光与粒子束, 2018, 30:046002 doi: 10.11884/HPLPB201830.170222Shen Jingwen, Hu Ye, Zheng Yu, et al. Three-dimensional Monte Carlo transport code JMCT in shielding engineering application[J]. High Power Laser and Particle Beams, 2018, 30: 046002 doi: 10.11884/HPLPB201830.170222 [17] Verst C G. Evaluation of shielding efficacy of a ferrite containing ceramic material[R]. Washington: Savannah River Site (SRS), Aiken, SC (United States), Savannah River National Lab (SRNL), 2015. [18] Holmes R L, White S W. Standardized unclassified Little Boy amd Fat Man outputs[R]. 2013.