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Management of carbon dioxide released from spent nuclear fuel through voloxidation
Journal of Radioanalytical and Nuclear Chemistry ( IF 1.5 ) Pub Date : 2021-09-04 , DOI: 10.1007/s10967-021-07972-w
Seok-Min Hong 1 , Hong Jang 1 , Siwan Noh 1 , Hyun Woo Kang 1 , Yung-Zun Cho 1
Affiliation  

The management of radioactive carbon (C-14) from spent nuclear fuel (SNF) in a voloxidation process is vital to prevent radioactive contamination of the environment. Thus, a double alkali method was applied to absorb the gaseous phase of C-14 (CO2) and to immobilize radioactive carbon into a stable structure. Based on the two-film theory, mass transfer and enhancement factor were evaluated for CO2 absorption in NaOH solution with regards to the effects of operating conditions such as the solution concentration, CO2 partial pressure, and gas flow rate on the absorbing performance. The absorption tests were carried out targeting the successful capture of CO2 released from SNF with a high decontamination factors (DF) more than 103. Causticization with Ca(OH)2 leads to the immobilization of absorbed carbon into a scalenohedral calcite (CaCO3) crystal, and its stable and nonporous characteristics suggested that calcite is a suitable structure for preparing waste forms stored in a geological repository.



中文翻译:

通过挥发氧化处理从乏核燃料中释放的二氧化碳

在挥发氧化过程中对来自乏核燃料 (SNF) 的放射性碳 (C-14) 的管理对于防止环境受到放射性污染至关重要。因此,采用双碱法吸收气相C-14(CO 2)并将放射性碳固定为稳定结构。基于双膜理论,从溶液浓度、CO 2分压、气体流量等操作条件对吸收性能的影响,评价了NaOH溶液中CO 2吸收的传质和增强因子。进行吸收测试的目标是成功捕获从 SNF 释放的 CO 2具有超过 10 的高去污因子 (DF)3 . Ca(OH) 2苛化导致吸附的碳固定为偏三角面体方解石 (CaCO 3 ) 晶体,其稳定和无孔的特性表明方解石是制备储存在地质储存库中的废物形式的合适结构。

更新日期:2021-09-04
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