CAJ | 학술논문

自然界中236 U与238 U原子个数比约10-14，不同反应堆类型及核燃料辐照情况辐照后的核材料中236 U与238 U原子个数比不同，一般为天然236 U与238 U原子个数比的107～1011倍。通过测量环境样品中的236 U与238 U原子个数比可探知取样点附近进行过的辐照活动、环境污染的来源及对应核燃料的燃耗。本研究使用配制的模拟样品，建立了多接收电感耦合等离子质谱（MC-ICP-MS）技术测定236 U与238 U原子个数比的方法以及估算核燃料燃耗的工作方案，并与其他燃耗计算方法比较，燃耗的相对偏差约10％。
자연계중236 U여238 U원자개수비약10-14，불동반응퇴류형급핵연료복조정황복조후적핵재료중236 U여238 U원자개수비불동，일반위천연236 U여238 U원자개수비적107～1011배。통과측량배경양품중적236 U여238 U원자개수비가탐지취양점부근진행과적복조활동、배경오염적래원급대응핵연료적연모。본연구사용배제적모의양품，건립료다접수전감우합등리자질보（MC-ICP-MS）기술측정236 U여238 U원자개수비적방법이급고산핵연료연모적공작방안，병여기타연모계산방법비교，연모적상대편차약10％。
The ratio of 236 U and 238 U atom number is different depending on the type of reactor and the status of irradiation of nuclear materials ,w hich is usual 107-1011 times than that in nature .The irradiation activity near sampling spots ,the source of irradia-tion contamination ,and the burnup of spent nuclear fuel can be explored by measuring ratio of 236 U and 238 U atom number in environmental samples .T he method of measuring ratio of 236 U and 238 U atom number in simulated samples by MC-ICP-MS and the working schedule for estimating burnup of spent nuclear fuel have been established . Compared with the other methods ,the relative deviation of burnup is about 10% .