Th-232的裂变和增殖性能实验研究

项目名称： Th-232的裂变和增殖性能实验研究

项目编号： No.91326104

项目类型： 重大研究计划

立项/批准年度： 2014

项目学科： 数理科学和化学

项目作者： 龚建

作者单位： 中国工程物理研究院核物理与化学研究所

项目金额： 90万元

中文摘要： 第四代核电站的一类就是利用Th-U循环，但是相对于U-Pu循环，其实验数据还比较缺乏，后处理过程中需要的基本参数（如剂量、裂变产物、长寿命次锕系核素的数据等）还不完全明确。本研究拟利用能谱和注量确定的快中子临界装置的中子场辐照Th-232样品，通过Th-232裂变电离室法、活化法和固体径迹探测器法等测量裂变碎片、Pa-233、U-233、长寿命次锕系核素等的特征γ射线，获得Th-232的裂变性能，U-233的生成率，辐照后的Th-232样品的剂量等，并用这些实验数据检验ENDF、JENDL、CENDL等数据库的参数，提出数据改进的建议；获得裂片元素和长寿命次锕系核素的产生率，为Th基反应堆嬗变长寿命核素的设计提供基础数据；获得辐照后的Th-232样品的辐射剂量情况，为后处理提供数据。本项研究获得的结果可以为Th-U循环反应堆设计等提供支撑。

中文关键词： Th-U循环；快中子；测量；裂变与俘获反应；增殖

英文摘要： Th-U fuel circle as one of the important design of Generation IV reactor systems, has received lots of interest. Unfortunately, the quality of nuclear data for the Th-U fuel circle is lower than for the comparable materials in the Pu-U circle. Some basic data such as the dose, fission product and long-lived actinides that the reprocessing needed are not clear. This research is going to study the sample of 232Th irradiated by a fast neutron critical reactor with specified neutron flux and energy spectrum. Using fission chamber, neutron activation method and solid track detector etc, the characterized γrays of fission fragments, 233Pa, 233U, long-lived minor actinides are measured，and the fission performance of 232Th, the production rate of 233U, the dose of irradiated 232Th sample are acquired, which is supportive to verifying the data from ENDF, JENDL, CENDL database and providing suggestions to improve these databases, and the design of Th-based reactor for the transmutation of long lived products, and the reprocessing of spent fuel, respectively. The result of this research is capable of supporting the design of the Th-U circle reactor.

英文关键词： Th-U fuel cycle；fast neutron；measurement；fission and capture reaction；multiplication