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U-Pu混合氧化物(Mixed oxide,MOX)燃料应用前景广阔。以国内M310型堆芯为对象,对使用30%MOX燃料的部分低泄漏堆芯燃料管理方案进行分析,比较了含MOX燃料堆芯和传统的全UO2燃料堆芯在平衡循环下压力容器快中子注量、原子位移次数(Displacement per atom,DPA)和辐照监督管超前因子的特性差异。结果表明,与国内主流的高泄漏全UO2燃料堆芯平衡循环相比,平衡循环压力容器内表面快中子注量率和DPA率小20%左右,343°处的辐照监督管快中子注量率小8%,超前因子大15%;与国内占少数比例的低泄漏全UO2燃料堆芯平衡循环相比,平衡循环压力容器内表面快中子注量率和DPA率大40%左右。进一步分析发现,虽然同等功率下MOX燃料比UO2燃料释放的中子多7%,但与国内主流的高泄漏全UO2燃料堆芯相比,部分低泄漏MOX燃料堆芯的燃料管理方式使堆芯外围组件功率降低,使得压力容器受到的快中子辐照损伤降低。
U-Pu Mixed Oxide (MOX) fuels are promising. Based on the domestic M310 core, a partial low-leakage core fuel management scheme using 30% MOX fuel was analyzed. The comparison between the MOX fuel core and conventional UO2 fuel core under pressure equalization cycle Differences between sub-fluence, Displacement per atom (DPA) and irradiation supervisor tube lead factor. The results show that the fast neutron fluence rate and DPA rate on the inner surface of a balanced recycle pressure vessel are about 20% smaller than those of the mainstream mainstream high-leakage UO2 fuel core balance and the irradiation supervisory tube at 343 ° fast neutron Compared with the low-leaking UO2 fuel core balance cycle in China, the fast neutron fluence rate and DPA rate on the inner surface of the balance-cycle pressure vessel are about 40% larger . Further analysis found that while MOX fuel delivered 7% more neutron than UO2 fuel at equivalent power, the fuel management of some of the low-leaking MOX fuel cores compared to the domestic mainstream high-leakage UO2 fuel core made the core Peripheral components reduce power, making the pressure vessel by fast neutron irradiation damage.