Analysis of CANDU Reactor Performance Using Thorium Fuel:Comparison with Natural UO2 Case  

作　　者：Ali Yehia Ellithi Afrah AL-Khawlani 

机构地区：[1]Faculty of Science,Cairo University,Cairo 12613,Egypt [2]Department of Alternative Energy Technology,Philadelphia University,Amman 19392,Jordan [3]Physics Department,Faculty of Science,Sana’a University,Sana’a 72738,Yemen

出　　处：《材料科学与工程（中英文B版）》2020年第4期139-147,共9页Journal of Materials Science and Engineering B

摘　　要：The purpose of the paper is to study the performance of the CANDU(Canada Deuterium Uranium)reactor when the reactor core is loaded with thorium fuel mixed with plutonium isotopes with ratio 3 and 5%.A three dimensional model is designed for the core of CANDU reactor.The computer code MCNPX(Monte Carlo N–Particle Transport)is used to calculate the processes in its core.The results are compared with natural UO2 case which is the typical fuel of the reactor.The results show that the multiplication factor of the reactor is higher even in the case of thorium fuel mixed with 3%plutonium isotopes,which indicates longer neutron life cycle length and more economic utilization of the reactor.

关 键 词：CANDU reactor MCNPX code reactor burn up natural uranium thorium fuel 

分 类 号：TL2[核科学技术—核燃料循环与材料]