内巴斯回旋加速器设施掩体壁预期诱发放射性的评估

A. Demerdjiev, D. Tonev, N. Goutev, D. Dimitrov, G. Dimitrova, E. Geleva, S. Genchev
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引用次数: 0

摘要

保加利亚科学院的核研究和核能研究所正在建造一个回旋加速器中心。Оne设计回旋加速器中心辐射防护的挑战之一是对该设施在使用寿命期间将产生的放射性废物的预期数量进行初步评估。本文的目的是对该设施运行20年后回旋加速器掩体壁的预期诱导放射性进行估计。为此,使用FLUKA代码进行蒙特卡罗模拟。得到了所产生的放射性核素在混凝土壁上的比活度分布和掩体内的残留剂量率分布。对碉堡混凝土壁上最重要的长寿命放射性核素154Eu、152Eu、134Cs、60Co、54Mn的比活度进行了估算。在这些结果的基础上,提出了屏蔽设计的优化,以减少在设施寿命期间产生的放射性废物的数量。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
ASSESSMENT OF THE EXPECTED INDUCED RADIOACTIVITY IN THE BUNKER WALLS AT THE INRNE-BAS CYCLOTRON FACILITY
The Institute for Nuclear Research and Nuclear Energy at the Bulgarian Academy of Sciences is working on the construction of a cyclotron centre. Оne of the challenges in designing the radiation protection of a cyclotron centre is the preliminary assessment of the expected amounts of radioactive waste that will be generated during the lifetime of the facility. Our aim in this paper is to make an estimation of the expected induced radioactivity in the cyclotron bunker walls after the 20 year operational period of the facility. For this purpose, Monte Carlo simulations with the code FLUKA were performed. The distributions of the specific activity of the generated radionuclides in the concrete walls and of the residual dose rates inside the bunker are obtained. The specific activity of the most important long-lived radionuclides in the concrete walls of the bunker, namely 154Eu, 152Eu, 134Cs, 60Co, 54Mn is estimated. On the basis of these results an optimization of the shielding design is proposed in order to decrease the amount of radioactive waste which will be generated during the facility lifetime.
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