Computational analysis of neutronic effects of ThO_2 rods loaded in CANDU 6 fuel assemblies  

作　　者：Seyed Mohammad Mirvakili Zohreh Gholamzadeh Seyed Amir Hossein Feghhi 

机构地区：[1]Reactor Research School, Nuclear Science and Technology Research Institute [2]Department of Radiation Application, Shahid Beheshti University,G.C

出　　处：《Nuclear Science and Techniques》2016年第4期14-20,共7页核技术（英文）

摘　　要：Thorium as a suitable fertile with higher natural resources in comparison with uranium resources has been remarkably considered by different nuclear energy user countries in the last decades. Its prominent features such as suitable possibility for power flattening of a nuclear reactor, applicable breeder blanket to produce^(233)U fissile as well as neutron leakage prevention from a nuclear core has caused its application as power flatter, breeder material or other aimed utilizations be evaluated by the researches. In the present study, neutronics of a modeled CANDU 6loaded with Th O_2 and UO_2fuel rods have been computationally studied. The study aimed at reprocessing of burned Th O_2 seeds at CANDU 6 reactor to recover the total produced uranium, which is to be going under another compound fuel cycle. The obtained results showed all the core reactivity coefficients are sufficiently negative. The modeled core 949 GWd burn-up concluding in 99.99 %depletion of^(235)U initial loads. 18.38 kg of^(233) U was produced in the burnt Th O_2 fuel after 1-year burn-up time. In addition, 31.84 kg of^(239) Pu was produced in the UO_2 spent fuel rods after the burn-up time. After a proposed cooling time, about 50.01 kg of^(233)U will be available in the spent Th O_2 fuel.Thorium as a suitable fertile with higher naturalresources in comparison with uranium resources has beenremarkably considered by different nuclear energy usercountries in the last decades. Its prominent features such assuitable possibility for power flattening of a nuclear reactor,applicable breeder blanket to produce 233U fissile aswell as neutron leakage prevention from a nuclear core hascaused its application as power flatter, breeder material orother aimed utilizations be evaluated by the researches. Inthe present study, neutronics of a modeled CANDU 6loaded with ThO2 and UO2 fuel rods have been computationallystudied. The study aimed at reprocessing of burnedThO2 seeds at CANDU 6 reactor to recover the total produceduranium, which is to be going under another compoundfuel cycle. The obtained results showed all the corereactivity coefficients are sufficiently negative. The modeledcore 949 GWd burn-up concluding in 99.99 %depletion of 235U initial loads. 18.38 kg of 233U was producedin the burnt ThO2 fuel after 1-year burn-up time. Inaddition, 31.84 kg of 239Pu was produced in the UO2 spentfuel rods after the burn-up time. After a proposed coolingtime, about 50.01 kg of 233U will be available in the spentThO2 fuel.

关 键 词：CANDU堆 中子泄漏 燃料组件 稳定杆 计算 核反应堆 燃烧时间 自然资源 

分 类 号：TL352[核科学技术—核技术及应用]