CAJ | 학술논문

安全壳内放射性核素浓度的计算是确定安全壳辐射剂量率的重要环节，而安全壳辐射剂量率是堆芯损伤评价的重要参数之一。本文利用ORIGEN2程序，采用简化分析法和间接计算法分别对事故后3种典型核素在安全壳内的浓度进行分析计算，并对两种方法的可用性进行了讨论。根据分析可知，间接计算法能够更好的模拟核素的释放、衰变以及相互转化过程，建议在事故早期堆芯损伤评价过程中使用。但是若考虑事故发生较长时间后的安全壳内核素浓度，短半衰期核素影响已经很小，简化分析法是可用的。
안전각내방사성핵소농도적계산시학정안전각복사제량솔적중요배절，이안전각복사제량솔시퇴심손상평개적중요삼수지일。본문이용ORIGEN2정서，채용간화분석법화간접계산법분별대사고후3충전형핵소재안전각내적농도진행분석계산，병대량충방법적가용성진행료토론。근거분석가지，간접계산법능구경호적모의핵소적석방、쇠변이급상호전화과정，건의재사고조기퇴심손상평개과정중사용。단시약고필사고발생교장시간후적안전각내핵소농도，단반쇠기핵소영향이경흔소，간화분석법시가용적。
Calculation of containment radionuclide concentration is an important part of estimating containment radiation dose rate ,and the latter is a primary parameter for core damage assessment .This paper provides the calculation of concentration of three typical nuclides within containment post-accident in both simplified analyt-ical method and indirect method with ORIGEN 2 code .The results show that the indirect method can simulate the release and decay of radionuclides and the transformation among them ,and suggests it can be used in the early core damage assessment .But if the containment radionuclide concentration is evaluated after a long time since the accident ,when the nuclides with short half-lives have little effects on the result ,the simplified meth-od is appropriate .