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为了研究利用西安脉冲堆(XAPR)热中子开展99Tc、129I嬗变的可行性,对乏燃料中长寿命裂变产物(LLFP)99Tc和129I核素的热中子嬗变计算方法进行理论与实验研究。利用NJOY程序,以ENDF/B VII.0库为基础,制作99Tc和129I在XAPR堆芯辐照温度下的蒙特卡罗程序(MCNP)截面库,并分析不同参数对截面数据的影响。采用ACE(A Compact ENDF)格式截面库和燃耗程序CINDER’90自带的63群活化截面,利用MCNP程序对ORIGEN2数据库中99Tc和129I的辐射俘获截面进行修正,用ORIGEN2程序分析一定规格的99Tc和129I靶件在XAPR内辐照后的嬗变情况。与实验结果值进行比较,截面数据的差异主要来自中子注量率测量值与实际值的误差,结果证明利用XAPR开展99Tc和129I嬗变是可行的。
In order to study the feasibility of 99Tc and 129I transmutation using XAPR thermal neutrons, theoretical and experimental studies on the calculation methods of thermal neutron transmutation of spent spent long-lived fission products (LLFP) 99Tc and 129I nuclides were carried out. The library of Monte Carlo (MCNP) cross sections of 99Tc and 129I at XAPR core irradiation temperature was prepared based on the ENDF / B VII.0 library using the NJOY program and the effect of different parameters on cross section data was analyzed. Using ACE (A Compact ENDF) format library and burn-in program CINDER’90, 63 groups of activated cross sections were taken. The MCNP program was used to correct the 99Tc and 129I radiation capture cross sections in ORIGEN2 database. ORIGEN2 program was used to analyze 99Tc And 129I target in the XAPR irradiation after transmutation. Compared with the experimental results, the difference of the cross-section data mainly comes from the error between the measured value and the actual value of the neutron fluence rate. The results show that it is feasible to use XAPR to carry out 99Tc and 129I transmutation.