[1] Liu Xiaohong, Wang Weili, Meng Tao, . Research on 3D spatial data models for early nuclear radiation damage effects and slitting algorithm[J]. Fire Control & Command Control, 37, 190-192,197(2012).

[2] Chen Yingqi, Chen Lingyan, Zhang Zhe, . The absorption coefficient of materials and thickness measurement by γ-ray energy spectrum analysis[J]. Journal of Isotopes, 17, 21-26(2004).

[3] Zhou Jianliang, Lü Yang, Cheng Xiaolong, . Study of the unknown line absorption coefficient of material by MCNP program and γ-ray energy spectrum analysis[J]. Science Technology and Engineering, 13, 6580-6582,6620(2013).

[4] Singh K J, Kaur S, Kaundal R S. Comparative study of gamma ray shielding and some properties of PbO–SiO₂–Al₂O₃ and Bi₂O₃–SiO₂–Al₂O₃ glass systems[J]. Radiation Physics and Chemistry, 96, 153-157(2014).

[5] Abutalib M M, Yahia I S. Novel and facile microwave-assisted synthesis of Mo-doped hydroxyapatite nanorods: characterization, gamma absorption coefficient, and bioactivity[J]. Materials Science and Engineering: C, 78, 1093-1100(2017).

[6] 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, 34, 201-221(2014).

[7] Rammah Y S, Mahmoud K A, Mohammed F Q, et al. Gamma ray exposure buildup factor and shielding features for some binary alloys using MCNP-5 simulation code[J]. Nuclear Engineering and Technology, 53, 2661-2668(2021).

[8] Khattab K, Boush M, Alkassiri H. Dose mapping simulation using the MCNP code for the Syrian gamma irradiation facility and benchmarking[J]. Annals of Nuclear Energy, 58, 110-112(2013).

[9] Wang M J, Sheu R J, Peir J J, et al. Criticality calculations of the HTR-10 pebble-bed reactor with SCALE6/CSAS6 and MCNP5[J]. Annals of Nuclear Energy, 64, 1-7(2014).

[10] Hamzah A, Kuntoro I. Desain konseptual perisai radiasi reaktor RRI-50[J]. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 17, 99-110(2015).

[11] [11] Erwin W J. Verification validation of Monte Carlo NParticle 6 f computing gamma protection facts[D]. WrightPatterson Air Fce Base: Air University, 2015.

[12] El Ouahdani S, Boukhal H, Erradi L, et al. Monte Carlo analysis of KRITZ-2 critical benchmarks on the reactivity temperature coefficient using ENDF/B-VII. 1 and JENDL-4.0 nuclear data libraries[J]. Annals of Nuclear Energy, 87, 107-118(2016).

[13] Abrefah R G, Essel P A A, Odoi H C. Estimation of the dose rate of nuclear fuel of Ghana Research Reactor-1 (GHARR-1) using ORIGEN-S and MCNP 6[J]. Progress in Nuclear Energy, 105, 309-317(2018).

[14] Hamzah A, Suwoto, Adrial H. Preliminary analysis of dose rates distribution of experimental power reactor 10 MW using MCNP[J]. Journal of Physics:Conference Series, 1198, 022038(2019).

[15] [15] Knoll G F. Radiation detection measurement[M]. 4th ed. Hoboken: John Wiley & Sons, 2010.

[16] Fang Zhigang, Liu Bin, Li Guoming, . Requirement and development analysis of warship equipment materials system[J]. Materials China, 33, 385-393(2014).

[17] Wu Shidong. Introduction to high strength and corrosion resistant aluminum alloy of ships developed by the US navy[J]. Journal of Unmanned Undersea Systems, 13, 49-52(2005).

[18] Han Liangwen, Gao Yedong, Xia Xinghan, . Passive efficiency calibration of HPGe detector based on MCNP[J]. Nuclear Safety, 19, 76-80(2020).

[19] Leung J K C. Application of shielding factors for protection against gamma radiations during a nuclear accident[J]. IEEE Transactions on Nuclear Science, 39, 1512-1518(1992).