摘要
聚变-裂变混合能源堆包括聚变中子源和次临界能源堆,主要目标是生产电能。回顾了国内外混合堆的发展历史,给出混合能源堆设计的边界条件和约束条件,说明次临界能源堆以铀锆合金为燃料、水为冷却剂的设计思想。利用输运燃耗耦合程序MCORGS计算了混合能源的燃耗,给出了中子有效增殖因数、能量放大倍数和氚增殖比等物理量随时间的变化。通过分析能谱和重要核素随燃耗时间的变化,说明混合能源堆与核燃料增殖、核废料嬗变混合堆的不同特点。论述了混合堆的热工设计并进行了安全分析。对于燃耗数值模拟程序,通过多家对算,保证其计算结果的可信性。针对次临界能源堆的特点,利用贫铀球壳建立了贫铀聚乙烯装置和贫铀LiH装置,并且专门设计加工了天然铀装置,开展铀裂变率、造钚率、产氚率等中子学积分实验,验证了数值模拟的可靠性。
In this paper, we propose a preliminary design for a fusion-fission hybrid energy reactor （FFHER）, based on current fusion science and technology and well-developed fission technology. Design rules are listed and a primary concept blanket with uranium alloy as fuel and water as coolant is put forward. The uranium fuel can be natural uranium, LWR spent fuel, or depleted uranium. The FFHER design can increase the utilization rate of uranium in a comparatively simple way to sustain the development of nuclear energy. The interaction between the fusion neutron and the uranium fuel with the aim of achieving greater energy multiplication and tritium sustainability is studied. Other concept hybrid reactor designs are also reviewed. Integral neutron experiments were carried out to verify the credibility of our proposed physical design. The combination of the physical design with the related thermal hydraulic design, alloy fuel manufacture, and nuclear fuel cycle programs provides the science and tech- nology basis for future development of the FFHER concept in China.
出处
《强激光与粒子束》
EI
CAS
CSCD
北大核心
2014年第10期21-31,共11页
High Power Laser and Particle Beams
基金
国家磁约束核聚变能研究专项(2010GB111001)
关键词
聚变-裂变混合堆
热工水力
燃料循环
中子学积分实验
fusion-fission hybrid reactor
thermal-hydraulic
fuel circulation
integral neutron experiment
作者简介
作者简介：李茂生（1963-），男，博士，从事中子输运、反应堆物理研究；li_maosheng@iapcm．ac．cn。
