无同位素分离的RSG-GAS中微量锕系元素焚烧的初步研究

R. A. P. Dwijayanto, M. Alfarisie
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引用次数: 1

摘要

核电厂产生的微量锕系元素由于其相当长的半衰期,在乏燃料管理中经常被认为是一个麻烦。处理放射性物质的一种有效策略是将其焚烧,以降低其放射性。本文介绍了在RSG-GAS研究堆中进行MA焚烧的研究。与以前的研究不同,这项工作没有将MA分离成单独的同位素,而是作为一个整体焚烧。采用ORIGEN2.1代码计算RSG-GAS堆芯内的MA焚烧量。本研究中使用的MA组成由Np、Am和Cm同位素组成。RSG-GAS的中心照射位置(CIP)装载6 kg MA,照射2年。结果表明,经过两年的辐照后,约有1kg的MA被焚烧,占初始浓度的18.87%。然而,与未辐照的MA相比,Cm-242同位素的增加以及新形成的Pu同位素显著增加了短期放射性。因此,两年的MA焚烧不能被认为是有效的,必须采取其他策略。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Preliminary Study on Minor Actinide Incineration in RSG-GAS without Isotope Separation
Minor actinides (MA) resulted from nuclear power plants is often considered as nuisance in spent fuel management due to its considerably long half-life. One of available strategies to deal with MA is to incinerate it, in order to reduce its radioactivity. This paper presents a study on MA incineration in RSG-GAS research reactor. Unlike previous study, this work did not separate the MA into individual isotopes, but incinerated as a whole. ORIGEN2.1 code is employed to calculate MA incineration within RSG-GAS core. MA composition used in this study consists of Np, Am, and Cm isotopes. The Central Irradiation Position (CIP) of RSG-GAS is loaded by 6 kg of MA and irradiated for two years. The result shows that about 1 kg of MA were incinerated after two years of irradiation, or 18,87% of the initial concentration. However, the increase of Cm-242 isotope, along with newly-formed Pu isotopes, were found to be significantly increasing short-term radioactivity compared to un-irradiated MA. Thus, two years-worth of MA incineration cannot be considered as effective, and other strategies must be pursued.
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