INFLUENCE OF DIFFERENT NATURAL FIBER-BASED COMPOSITES USE AS A FILLER FOR CRACKING IN NUCLEAR REACTOR BIOLOGICAL SHIELDS

A. El-Sawy
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Abstract

The biological shield is very important in the nuclear power reactor, so it is necessary to study the effect of crack on it. This work aims to study fiber composites as a radiation shielding for various purposes associated with nuclear installations, as properly as a repairing mixture for developing cracks in the biological shields of a nuclear power reactor. In this study, the MCNP-5 model of a pressurized water reactor (PWR) was used. Four different fiber composites of natural fiber (FP) (ρ= (1.373 g/ m3), fiber with lead (FPPb) (ρ=2.756 g /cm3), cement fiber (CF) (ρ=2.095 g/ m3) and cement-fiber-magnetite (CFM) (ρ =2.858 g /cm3) were used as the filler materials for cracking in the biological shield. The total mass attenuation coefficients µm for the studied composites have been calculated by the Win X-Com program of gamma-ray at an energy range from 0.15 – 20 MeV. Neutron and gamma-ray fluxes and dose rates were calculated through different distances of the reactor shields for different fiber composites. Total dose rates through biological shield without cracking and after cracking have been calculated. Radiation Protection Efficiency (RPE %) for all samples at the outer surface of the biological shield was calculated. The results showed that by using fiber composites as a filler for cracking, the values of flux and dose rate for neutrons and gamma-rays have decreased. Also, FPPb is the best material for gamma-ray because it contains lead, which has a high atomic number. While CFM has the best material shield for neutron and gamma-ray in addition to magnetite and boron carbide the properties of CFM composite were improved. Max. value of RPE % for FPPb was (43.1%), then CFM (37.2%), Fp (30.2%) and CF (20.2%). From these results, it can be concluded that plastic fiber composites were the best materials that can be used as a filler in the biological shield of nuclear power reactors.
不同天然纤维基复合材料作为核反应堆生物屏蔽体裂缝填料的影响
生物屏蔽在核反应堆中非常重要,因此有必要研究裂纹对其的影响。本工作旨在研究纤维复合材料作为核设施相关各种用途的辐射屏蔽,以及作为修复核反应堆生物屏蔽裂纹的混合物。在本研究中,使用了压水堆(PWR)的MCNP-5模型。使用四种不同的纤维复合材料,即天然纤维(FP)(ρ=(1.373 g/m3)、含铅纤维(FPPb)(ρ=2.756 g/cm3)、水泥纤维(CF)(ρ=20.95 g/m3)和水泥纤维磁铁矿(CFM)(ρ=2.858 g/cm3)作为生物屏蔽中开裂的填充材料。所研究的复合材料的总质量衰减系数µm已通过Win X-Com程序计算出能量范围为0.15–20 MeV的伽马射线。针对不同的纤维复合材料,通过反应堆屏蔽层的不同距离计算了中子和伽马射线通量和剂量率。已经计算了在没有破裂和破裂后通过生物屏蔽的总剂量率。计算了生物屏蔽外表面所有样品的辐射防护效率(RPE%)。结果表明,使用纤维复合材料作为裂化填料,中子和伽马射线的通量和剂量率值都有所降低。此外,FPPb是伽马射线的最佳材料,因为它含有高原子序数的铅。CFM除了具有磁铁矿和碳化硼外,还具有最好的中子和伽马射线屏蔽材料,CFM复合材料的性能得到了改善。FPPb的RPE%最大值为(43.1%),其次为CFM(37.2%)、Fp(30.2%)和CF(20.2%)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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