Compact shielding design of a portable 241Am–Be source. (October 2017)

• Record Type: Journal Article
• Authors: Zhang, Feng; Wu, He; Wang, Xinguang; Wu, Guoli; Jia, Wenbao; Ti, Yongzhou
• Is Part Of: Applied radiation and isotopes. Volume 128(2017:Oct.)
• Page Start: 49
• Page End: 54
• Publication Date: 2017-10
• Subjects: Nuclear well logging -- 241Am–Be source -- Dose rate -- Composite material shielding -- Monte Carlo simulation; Radiology -- Periodicals; Radiation -- Industrial applications -- Periodicals; Nuclear chemistry -- Periodicals; Internet resource; Periodical; 660.298
• DOI: 10.1016/j.apradiso.2017.06.033
• Languages: English
• ISSNs: 0969-8043

Abstract

Abstract: A compact shielding tank for portable 241 Am–Be neutron source, which is used in nuclear well logging, was designed according to the Monte Carlo simulation. From inner to outer, the proposed tank has two shielding layers to shield the high- and low-energy neutrons. In this study, the shielding properties of several materials were evaluated. Tungsten was selected as the neutron moderator to build the inner layer. The thermal neutron absorber in the outer layer was made of polyethylene containing 1.2% boron carbide. The volume and weight of the new tank reduced by 86% and 54%, respectively, by using this dual-layer shielding model, when compared with those of the old shielding tank. Moreover, the simulation results indicated that the total dose rate anywhere outside the tank is less than 0.025 mSv/h and that the intensity of gamma flux at the tank surface becomes lower. Highlights: Compact shielding design of a portable 18 Ci 241 Am–Be source. Tungsten and polyethylene containing 1.2% boron carbide were selected as the composite shielding material. We achieved 86% and 54% reduction in the volume and weight of the shielding tank, respectively. A reduced dose rate less than 0.025 mSv/h was observed outside the shielding tank.