CAJ | 학술논문

中子和γ射线源强是辐射屏蔽设计的基本输入数据，研究堆芯中子和γ射线源强的变化有助于工作人员在维修和换料期间进一步做好辐射防护。论文通过ORIGEN-S调用不同的数据库建立了两种计算反应堆堆芯中子和γ射线源强的方法，对比了计算结果的差异，并分析了燃耗、富集度、比功率、运行方式对计算结果的影响。结果表明：在不同的停堆时间，采用ORIGEN-ARP计算的中子源强略小于采用CARD-IMAGE数据库计算的结果，差值在6％以内；两种方法对不同能群对应的γ射线源强产生的影响不同，且随着停堆时间的延长，影响增大；各因素对堆内中子源强产生了不同的影响，中子源强随燃耗的加深而逐渐增大，随着富集度和比功率的增大而减小，在燃耗相同且运行时间较长的情况下，间歇模式运行产生的中子源强高于连续模式下产生的中子源强40％～50％。
중자화γ사선원강시복사병폐설계적기본수입수거，연구퇴심중자화γ사선원강적변화유조우공작인원재유수화환료기간진일보주호복사방호。논문통과ORIGEN-S조용불동적수거고건립료량충계산반응퇴퇴심중자화γ사선원강적방법，대비료계산결과적차이，병분석료연모、부집도、비공솔、운행방식대계산결과적영향。결과표명：재불동적정퇴시간，채용ORIGEN-ARP계산적중자원강략소우채용CARD-IMAGE수거고계산적결과，차치재6％이내；량충방법대불동능군대응적γ사선원강산생적영향불동，차수착정퇴시간적연장，영향증대；각인소대퇴내중자원강산생료불동적영향，중자원강수연모적가심이축점증대，수착부집도화비공솔적증대이감소，재연모상동차운행시간교장적정황하，간헐모식운행산생적중자원강고우련속모식하산생적중자원강40％～50％。
Neutron and photon source intensity are input data for radiation protection shielding calculation, so it could help staff do better radiation protection during the maintenance and refueling to study the changes of neu-tron andγray source intensity in reactor.In this paper, the calculation method with two kinds of databases was studied by ORIGEN-S and the influence factors fuel burnup, enrichment, specific power and operation mode were analyzed.The results indicated that at different shutdown times, the neutron source intensities calculated by ORIGEN-ARP library were slightly less than that by CARD-IMAGE library, the difference was less than 6%.The effects of databases on the calculation results of different energyγray were different.With increasing of shutdown time, the difference ofγray source intensity calculated by the two databases grew.The various fac-tors affected the neutron source intensity differently.The neutron source intensity increased with burnup deepe-ning, and decreased as enrichment and specific power increased.In the same fuel burnup and long operation time condition, the neutron source intensity under intermittent operation mode was higher 40%-50%than that under continuous mode.