首页 | 本学科首页   官方微博 | 高级检索  
     

钍基柱状高温气冷堆不同启动燃料特性初步分析
引用本文:郑云涛,丁铭,张亮,王黎东,曹夏昕. 钍基柱状高温气冷堆不同启动燃料特性初步分析[J]. 原子能科学技术, 2013, 47(Z1): 216-220. DOI: 10.7538/yzk.2013.47.zk.0216
作者姓名:郑云涛  丁铭  张亮  王黎东  曹夏昕
作者单位:哈尔滨工程大学 核安全与仿真技术国防重点学科实验室,黑龙江 哈尔滨150001
摘    要:钍是一种可转换材料,将其转换成233U能极大提高现有核燃料资源的储量。为实现对钍的合理利用,以模块式柱状高温气冷堆GT-MHR的燃料组件作为研究对象,选取低浓缩铀、武器级钚、核反应堆级钚等作为其启动燃料。利用栅格输运计算程序DRAGON对这3种启动燃料下的钍基柱状燃料组件的寿期初中子能谱、无限增殖系数、燃耗、转换比以及233U和232Th的含量等参数进行了分析。结果表明,在易裂变物质初装量约为9%时,与低浓缩铀和武器级钚相比,核反应堆级钚作为启动燃料时组件寿期初中子能谱较硬、转换比较高;其燃耗达90 GW•d/tHM;其无限增殖系数在寿期内的波动最小;燃耗为75 GW•d/tHM时组件中233U存余量与232Th消耗量之比达0.566。

关 键 词:钍基MOX燃料   柱状高温气冷堆   低浓缩铀   武器级钚   核反应堆级钚

Preliminary Analysis of Different Driver Fuels in Thorium-Based Prismatic GT-MHR
ZHENG Yun-tao,DING Ming,ZHANG Liang,WANG Li-dong,CAO Xia-xin. Preliminary Analysis of Different Driver Fuels in Thorium-Based Prismatic GT-MHR[J]. Atomic Energy Science and Technology, 2013, 47(Z1): 216-220. DOI: 10.7538/yzk.2013.47.zk.0216
Authors:ZHENG Yun-tao  DING Ming  ZHANG Liang  WANG Li-dong  CAO Xia-xin
Affiliation:National Defense Key Discipline Laboratory of Nuclear Safety and Simulation Technology, Harbin Engineering University, Harbin 150001, China
Abstract:Thorium is a fertile material and is converted into 233U in nuclear reactors, which could greatly improve existing reserves of nuclear fuel resources. In order to use thorium, block-type modular high temperature gas-cooled reactor GT-MHR was studied, and low-enriched uranium, weapon-grade plutonium and reactor-grade plutonium were chosen as the driver fuels for the thorium based GT-MHR. The lattice transport code DRAGON was used to analyze the characteristics of the prismatic fuel block, including the neutron energy spectrum at beginning of life, infinite multiplication factor, fuel burnup, conversion ratio, and the mass of 233U and 232Th. The analysis shows that when the mass fraction of the initial fissile material is close to 9%, compared with the low-enriched uranium and weapon-grade plutonium, the reactor-grade plutonium has the hardest neutron energy spectrum at beginning of life and high conversion ratio, and reaches a burnup of 90 GW•d/tHM, and achieves the minimum reactivity swing during the fuel cycle. Moreover, the ratio of remaining 233U to the consumption of 232Th reaches 0.566 at a burnup of 75 GW•d/tHM.
Keywords:thorium-based MOX fuel  block-type high temperature gas-cooled reactors  low-enriched uranium  weapon-grade plutonium  reactor-grade plutonium
点击此处可从《原子能科学技术》浏览原始摘要信息
点击此处可从《原子能科学技术》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号