CAJ | 학술논문

加速器驱动的次临界系统（ADS ）在实现嬗变核废料方面具有良好的前景。对加速器驱动10 M W次临界快热耦合能谱气冷堆的物理方案进行了设计和研究，利用 MCNPX和ORIGEN耦合的计算程序COUPLE2.0对该方案进行了计算，其中，中子截面采用ENDF-7处理后得到的5个温度300、600、900、1500、2500 K下的连续能量核数据库。得到该方案350 d燃耗期间的 kef 、质子效率、缓发中子份额以及加速器束流强度的变化。进而计算得到了该方案的燃耗信息，并分析了该方案的嬗变能力。结果表明，该方案在350 d燃耗期间的 kef 、加速器束流强度变化较小，嬗变支持比为24.86，具有较好的嬗变效果。
가속기구동적차림계계통（ADS ）재실현선변핵폐료방면구유량호적전경。대가속기구동10 M W차림계쾌열우합능보기랭퇴적물리방안진행료설계화연구，이용 MCNPX화ORIGEN우합적계산정서COUPLE2.0대해방안진행료계산，기중，중자절면채용ENDF-7처리후득도적5개온도300、600、900、1500、2500 K하적련속능량핵수거고。득도해방안350 d연모기간적 kef 、질자효솔、완발중자빈액이급가속기속류강도적변화。진이계산득도료해방안적연모신식，병분석료해방안적선변능력。결과표명，해방안재350 d연모기간적 kef 、가속기속류강도변화교소，선변지지비위24.86，구유교호적선변효과。
The accelerator-driven sub-critical system has promising future in transmuta-tion of nuclear spent fuels .A physical design of a 10MW fast-thermal spectrum gas-cooled reactor was studied .The program COUPLE2.0 ,which couples with MCNPX and ORIGEN ,was applied to compute this scheme ,and the continuous energy neutron cross section was obtained by the nuclear data library of ENDF-7 which was modified with five different temperatures :300 ,600 ,900 ,1 500 ,and 2500K .The physical pa-rameters such as kef ,proton efficiency ,delayed neutron fraction and accelerator current varying with the burnup time were obtained .The system during 350 d burnup was obtained and the transmutation capability was analyzed by the further calculation .It is found that during the 350 d burnup ,the variations of kef and accelerator current are relatively small .The system has good transmutation capability with the transmutation support ratio of 24.86 .