Determination of the Activity Inventory in the Structural Components of the Dalat Nuclear Research Reactor for Its Decommissioning Planning

IF 1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY
Q. Tran, K. Nguyen, B. Luong, Ton-Nghiem Huynh, Q. Pham, Doan-Hai-Dang Vo, Nhi-Dien Nguyen
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引用次数: 0

Abstract

This report presents the methods and calculated results of the activity inventory in the structural components of the Dalat Nuclear Research Reactor (DNRR). These components include the shielding concrete, the reactor tank, and its inside irradiated facilities; the thermal and thermalizing columns; and the horizontal channels. The MCNP5 code with a three-dimensional neutron transport model was used to calculate the neutron flux distribution, neutron energy spectrum at different locations, and activation cross sections of long-lived radioactive nuclides in activated major materials, including heavy concrete, reflection graphite, and aluminum of the reactor. The calculated results of the energy spectrum and activation cross sections of MCNP5 were used in the ORIGEN2.1 point depletion code to calculate the neutron-induced activity of activated materials at different time points by modeling the irradiation history and radioactive decay. Radioactivity of long-lived key activation products such as 41Ca, 60Co, 55Fe, 63Ni, and 152Eu was modeled, and volumes of radioactive waste mainly of ordinary concrete, graphite, and aluminum in the structural components of the reactor were estimated. Experimental results of neutron flux and specific activities of some typical nuclides such as 60Co, 152Eu, 55Fe, and 63Ni in activated aluminum samples showed good agreement with the calculated results. As part of the national regulation requirements, the obtained data have been used to develop the decommissioning plan for the operational DNRR, with an estimation of about 10 years before its permanent shutdown.
达拉特核研究堆结构部件活动清单的确定及其退役计划
本文介绍了大叻核研究堆(DNRR)结构部件活度清单的计算方法和结果。这些部件包括屏蔽混凝土、反应堆储罐及其内部的辐照设施;热柱和热柱;还有水平通道。采用三维中子输运模型的MCNP5代码计算了反应堆重质混凝土、反射石墨、铝等活化主要材料中中子通量分布、不同位置的中子能谱和长寿命放射性核素的活化截面。将MCNP5的能谱和活化截面计算结果应用于ORIGEN2.1点耗尽代码中,通过模拟辐照历史和放射性衰变,计算不同时间点活化材料的中子诱导活度。模拟了41Ca、60Co、55Fe、63Ni和152Eu等长寿命关键活化产物的放射性,并估算了反应堆结构部件中以普通混凝土、石墨和铝为主的放射性废物的体积。60Co、152Eu、55Fe、63Ni等典型核素在活化铝样品中的中子通量和比活度实验结果与计算结果吻合较好。作为国家监管要求的一部分,所获得的数据已用于制定运行中的DNRR的退役计划,估计其永久关闭前约10年。
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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来源期刊
Science and Technology of Nuclear Installations
Science and Technology of Nuclear Installations NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.30
自引率
9.10%
发文量
51
审稿时长
4-8 weeks
期刊介绍: Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavor associated with the establishment and the growth of the journal is expected to lend support to the renaissance of nuclear technology in the world and especially in those countries where nuclear programs have not yet been developed.
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