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双排棒组件超临界水堆堆芯方案设计
引用本文:杨珏,张勇,赵传奇,单建强,王飞,曹良志.双排棒组件超临界水堆堆芯方案设计[J].西安交通大学学报,2012,46(9):78-82.
作者姓名:杨珏  张勇  赵传奇  单建强  王飞  曹良志
作者单位:1. 中科华核电技术研究院,518026,广东深圳
2. 西安交通大学能源与动力工程学院,710049,西安
基金项目:国家高技术研究发展计划资助项目(2009AA050705)
摘    要:结合国际上多种超临界水堆堆芯设计方案的优点,提出了一种新的压力容器式低泄漏堆芯设计方案,其特点是,堆芯中采用了双排棒正方形闭式燃料组件和三区低泄漏换料.双排棒燃料组件由两排燃料棒包围一个慢化剂水棒构成,可以使得慢化均匀;三区低泄漏换料可以大大延长堆芯寿期,降低压力容器快中子注量.通过堆芯三维物理热工耦合计算发现,该方案寿期内的最大包壳温度(MCST)为684℃,堆芯寿期为300个有效满功率天,且功率分布平坦.在此基础上,对所有组件进行了更为保守的子通道热工水力计算,得出MCST为685.3℃,进一步表明所提堆芯设计方案在物理热工方面是可行的.

关 键 词:超临界水堆  双排棒组件  低泄漏堆芯  热工水力分析

Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies
YANG Jue , ZHANG Yong , ZHAO Chuanqi , SHAN Jianqiang , WANG Fei , CAO Liangzhi.Concept Design of Supercritical Water Cooled Reactor Core with Double-Row-Rod Assemblies[J].Journal of Xi'an Jiaotong University,2012,46(9):78-82.
Authors:YANG Jue  ZHANG Yong  ZHAO Chuanqi  SHAN Jianqiang  WANG Fei  CAO Liangzhi
Institution:1.China Nuclear Power Technology Research Institute,Shenzhen,Guangdong 518026,China; 2.School of Energy and Power Engineering,Xi’an Jiaotong University,Xi’an 710049,China)
Abstract:A new pressure-vessel type supercritical water cooled reactor(SCWR) core concept was proposed by combining merits of several SCWR core designs in the world.This core design employs a new type of closed assembly with double-row fuel rods in square geometry and a three-batch low-leakage refueling scheme.The assembly consists of two rows of fuel rods and a moderator rod,which causes the moderation more uniform.The three-batch low leakage refueling scheme obviously increases the cycle length and reduces the neutron fluence on the pressure vessel.Three-dimensional neutronics/thermohydraulics coupling calculation shows that the maximum cladding surface temperature(MCST) is 684 ℃,the cycle life is 300 effective full power days and the power distribution is flat.Then the more conservative sub-channel analysis was performed for all fuel assemblies.The MCST was evaluated to be 685.3 ℃,showing that the core design is feasible.
Keywords:supercritical water cooled reactor  double-row-rod assembly  low leakage reactor core  thermal-hydraulic analysis
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