Fundamental Study of the Sulfide Reprocessing Process for Oxide Fuel (I) Study on the Pu, MA and FP Tracer-Doped U3O8
Fundamental Study of the Sulfide Reprocessing Process for Oxide Fuel (I) Study on the Pu, MA and FP Tracer-Doped U3O8
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氧化物燃料硫化物后处理工艺基础研究（一）Pu、MA、FP示踪剂掺杂U3O8的研究
DOI：
10.1080/18811248.2011.9711782
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发表时间：
2011
期刊：
影响因子：
--
通讯作者：
N. Sato
中科院分区：
文献类型：
--
作者：
A. Kirishima;T. Mitsugashira;T. Ohnishi;N. Sato
为了从乏核燃料中回收燃料材料，提出了一种基于裂变产物（FP）选择性硫化的新型后处理工艺，其中FP和次锕系元素（MA）首先被CS2气体硫化，然后用稀硝酸溶液溶解。因此，燃料元素以 UO2 和 PuO2 的形式回收。作为这一新概念的基础研究，本文利用236Pu-、237Np-、241Am-、152Eu-、137Cs-和85Sr掺杂的U3O8样品，通过γ射线和α能谱研究了U、Pu、Np、Am、Eu、Cs和Sr的硫化和溶解行为。结合硫化物相分析和溶解反应的化学热力学信息，研究并合理解释了各元素溶解率对硫化温度的依赖性。 350 至 450°C 的硫化温度似乎有利于从 U 和 Pu 中分离 FP 和 MA，因为在此温度范围内的硫化处理导致 FP 和 U 之间的溶解率存在明显差异。
For the recovery of fuel materials from spent nuclear fuel, a novel reprocessing process based on the selective sulfurization of fission products (FP) has been proposed, where FP and minor actinides (MA) are first sulfurized by CS2 gas, and then, dissolved by a dilute nitric acid solution. Consequently, the fuel elements are recovered as UO2 and PuO2. As a basic research of this new concept, the sulfurization and dissolution behaviors of U, Pu, Np, Am, Eu, Cs, and Sr were investigated by γ-ray and α spectrometries in this paper using 236Pu-, 237Np-, 241Am-, 152Eu-, 137Cs-, and 85Sr-doped U3O8 samples. The dependence of the dissolution ratio of each element on the sulfurization temperature was studied and reasonably explained by combining the information of the sulfide phase analysis and the chemical thermodynamics of the dissolution reaction. The sulfurization temperature ranging from 350 to 450°C seems to be promising for the separation of FP and MA from U and Pu, since a clear difference in the dissolution ratio between FP and U was derived by the sulfurization treatment in this temperature range.