CAJ | 학술논문

核数据是反应堆物理计算的基础数据,研究其不确定度对反应堆物理计算引入的不确定度,对提高反应堆的安全性和经济性具有重要意义。本文基于抽样理论研究了反应堆物理计算不确定度分析的方法,研发了不确定度分析程序 UNICORN。基于 ENDF/B-Ⅶ.1评价数据库,使用 NJOY 程序开发了多群协方差数据库。采用 UNICORN 程序和多群协方差数据库对三哩岛燃料棒和基准题 RB31的k∞进行了不确定度分析,得到核数据库中各分反应道截面的不确定度对k∞造成的不确定度。结果表明：238 U(n,γ)截面对三哩岛燃料棒k∞造成的不确定度最大,相对不确定度达0.4%左右；协方差数据库的不同来源会对不确定度分析结果造成一定影响。
핵수거시반응퇴물리계산적기출수거,연구기불학정도대반응퇴물리계산인입적불학정도,대제고반응퇴적안전성화경제성구유중요의의。본문기우추양이론연구료반응퇴물리계산불학정도분석적방법,연발료불학정도분석정서 UNICORN。기우 ENDF/B-Ⅶ.1평개수거고,사용 NJOY 정서개발료다군협방차수거고。채용 UNICORN 정서화다군협방차수거고대삼리도연료봉화기준제 RB31적k∞진행료불학정도분석,득도핵수거고중각분반응도절면적불학정도대k∞조성적불학정도。결과표명：238 U(n,γ)절면대삼리도연료봉k∞조성적불학정도최대,상대불학정도체0.4%좌우；협방차수거고적불동래원회대불학정도분석결과조성일정영향。
The nuclear data are the basic data for reactor physics calculation.It is signif-icant to study the contribution of their uncertainty to the uncertainty of reactor physics calculation for improving the safety and economy of reactor.Based on the ENDF/B-Ⅶ.1 library,the covariance library including the variance and covariance for all the basic cross sections and all the groups was generated using the NJOY code.The uncertainty analysis code UNICORN for reactor physics calculation was developed based on the statistical sampling method.Based on the UNICORN and covariance library,the uncer-tainties of k∞ for Three Mile Island (TMI)lattice and RB31 benchmark,due to the uncertainty of basic cross sections,were analyzed.The results indicate that the uncer-tainty of 238 U(n,γ)cross section is the largest uncertainty to the k∞ of TMI lattice and the relative uncertainty to the k∞ is up to about 0.4%,and different sources of covari-ance library effect the uncertainty of analysis result.