核技术
覈技術
핵기술
Nuclear Techniques
2015年
10期
100601-1-100601-6
,共1页
魏述平%李兰%程诗思%朱建平%谭怡
魏述平%李蘭%程詩思%硃建平%譚怡
위술평%리란%정시사%주건평%담이
U-Pu混合氧化物燃料%压力容器%快中子注量%原子位移次数%超前因子
U-Pu混閤氧化物燃料%壓力容器%快中子註量%原子位移次數%超前因子
U-Pu혼합양화물연료%압력용기%쾌중자주량%원자위이차수%초전인자
MOX%RPV%Fast neutron fluence%DPA%Forward factor
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混閤氧化物(Mixed oxide, MOX)燃料應用前景廣闊。以國內M310型堆芯為對象，對使用30% MOX燃料的部分低洩漏堆芯燃料管理方案進行分析，比較瞭含 MOX 燃料堆芯和傳統的全 UO2燃料堆芯在平衡循環下壓力容器快中子註量、原子位移次數(Displacement per atom, DPA)和輻照鑑督管超前因子的特性差異。結果錶明，與國內主流的高洩漏全UO2燃料堆芯平衡循環相比，平衡循環壓力容器內錶麵快中子註量率和DPA率小20%左右，343°處的輻照鑑督管快中子註量率小8%，超前因子大15%；與國內佔少數比例的低洩漏全UO2燃料堆芯平衡循環相比，平衡循環壓力容器內錶麵快中子註量率和DPA率大40%左右。進一步分析髮現，雖然同等功率下MOX燃料比UO2燃料釋放的中子多7%，但與國內主流的高洩漏全UO2燃料堆芯相比，部分低洩漏MOX燃料堆芯的燃料管理方式使堆芯外圍組件功率降低，使得壓力容器受到的快中子輻照損傷降低。
U-Pu혼합양화물(Mixed oxide, MOX)연료응용전경엄활。이국내M310형퇴심위대상，대사용30% MOX연료적부분저설루퇴심연료관리방안진행분석，비교료함 MOX 연료퇴심화전통적전 UO2연료퇴심재평형순배하압력용기쾌중자주량、원자위이차수(Displacement per atom, DPA)화복조감독관초전인자적특성차이。결과표명，여국내주류적고설루전UO2연료퇴심평형순배상비，평형순배압력용기내표면쾌중자주량솔화DPA솔소20%좌우，343°처적복조감독관쾌중자주량솔소8%，초전인자대15%；여국내점소수비례적저설루전UO2연료퇴심평형순배상비，평형순배압력용기내표면쾌중자주량솔화DPA솔대40%좌우。진일보분석발현，수연동등공솔하MOX연료비UO2연료석방적중자다7%，단여국내주류적고설루전UO2연료퇴심상비，부분저설루MOX연료퇴심적연료관리방식사퇴심외위조건공솔강저，사득압력용기수도적쾌중자복조손상강저。
Background:The mixed oxide (MOX) fuel is made from UO2 and PuO2 by post-processing of the spent duel of pressed water reactor (PWR). It has a good future for wide application but needs plenty of analyses of its characteristics prior to being used in the reactor.Purpose: This study aims to analyze the radiation characteristics of MOX fuel compared with the traditional core fuel.Methods: In accordance with the fuel management of M310 nuclear power plant (NPP) with 30% core filled with MOX fuel assemblies, fast neutron fluence, displacement per atom (DPA) rate on reactor pressure vessel (RPV) and forward factor of irradiation surveillance of the reactor core are studied and compared with both the traditional high leak reactor core with UO2 assemblies in equilibrium cycle and the low leak reactor core with UO2 assemblies which is minority in China.Results: The former comparison results show that the change of the fast neutron fluence and DPA rate on RPV are decreased by 20%, the fluence rate of irradiation surveillance in the direction of 343° is decreased by 8%, forward factor of irradiation surveillance in the direction of 343° is increased by 15%. The latter comparison results show that the change of the fast neutron fluence and DPA rate on RPV are increased by about 40%. Comparing the MOX fuel with the UO2 fuel on the same power level independently, it shows that MOX fuel releases 7% more fast neutron than UO2 fuel.Conclusion: The reactor core with MOX assemblies has less damage than the traditional high leak reactor core with UO2 assemblies.
