2050年前我国压水堆核燃料循环模式研究

Study of nuclear fuel cycle mode of PWR in China before 2050

根据中国工程物理研究院的《中国能源中长期(2030、2050)发展战略研究》报告,以我国的两种主流堆型—大亚湾M310和三代AP1000为研究对象,由我国核燃料循环现状和未来发展目标,假定了2050年前我国压水堆核燃料循环的几种可能模式,并利用DESAE-2(核能情景分析软件)计算了假定模式下的铀钚资源需求与高放废物的提取量。计算结果可为我国核能发展策略提供数据参考。计算结果的比较与分析表明,扩大装有MOX燃料的在运营压水堆规模能更有效地节省铀资源,而决定装有MOX燃料的在运营压水堆规模大小的关键在于所具有压水堆乏燃料后处理能力的大小。

Based on the medium and long-term development targets of nuclear power given by China Academy of Engineering Physics and current situation and future development goal of nuclear fuel cycle in China, the mainstream reactor types M310 and AP1000 as research objects, the possible scenarios of nuclear fuel cycle of PWR were assumed before 2050. The resource requirements for uranium and plutonium and high- level radioactive waste extraction yield in the assuming scenarios of nuclear fuel cycle were carried out by using DESAE-2 program. The results can provide a data reference to China＇s nuclear energy development strategy. A comparison and analysis of calculation results showed that expanding the scale of PWR loading MOX fuel is the key to improve spent fuel reprocessing power, it can saves the uranium resources significantly.