Bi2O3改性cao - k20 - p2o5玻璃体系的γ射线和中子屏蔽性能

Parminder Kaur, Kulbir Singh, M. Kurudirek, Sonika Thakur
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引用次数: 0

摘要

制备了含钙、钾铋改性磷酸盐玻璃体系,并对其作为核反应堆屏蔽伽马射线和中子的透明观察窗的适用性进行了评价。采用密度、XRD和FTIR技术对玻璃的结构进行了研究。利用XCOM和XMuDat程序对356和662 keV能量下的γ射线屏蔽性能进行了实验和理论研究,并与常用的重晶石混凝土进行了比较。并对暴露累积因子进行了研究。研究了其中子屏蔽性能,并与常用的几种中子屏蔽材料(碳化硼、聚乙烯颗粒和普通混凝土)进行了比较。结果表明,所研究的Bi2O3分数为0.2、0.25和0.3 wt的玻璃是屏蔽γ射线和中子的潜在候选材料。
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Gamma-ray and neutron shielding behaviour of CaO-K2O-P2O5 glass system modified with Bi2O3
Bismuth modified phosphate glass system containing calcium and potassium was prepared and assessed for its applicability as transparent viewing windows for shielding against gamma-rays and neutrons in nuclear reactors. The structure of the glasses was studied by density, XRD and FTIR techniques. The gamma-ray shielding properties were studied at energies 356 and 662 keV both experimentally and theoretically (by XCOM and XMuDat programs) and compared with commonly used barite concrete. Exposure buildup factor was also investigated. The neutron shielding properties were studied and compared with some common neutron shielding materials (Boron Carbide, Polyethylene grains and ordinary concrete). Results indicate that the studied glasses with 0.2, 0.25, 0.3 wt. fraction Bi2O3 are potential candidates for gamma-ray and neutron shielding applications.
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