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论文摘要

基于SIMULATE3程序对压水堆钍-钚燃料反馈性能及钚焚烧效率研究

A study of the feedback performance and plutonium burning efficiency of Th-Pu fuel in PWR using SIMULATE3 code

作者:樊兴(四川大学物理科学与技术学院);吴丽萍(四川大学物理科学与技术学院)

Author:FAN Xing(College of Physical Science and Technology, Sichuan University);WU Li-Ping(College of Physical Science and Technology, Sichuan University)

收稿日期:2014-01-15          年卷(期)页码:2015,52(1):113-116

期刊名称:四川大学学报: 自然科学版

Journal Name:Journal of Sichuan University (Natural Science Edition)

关键字:钍钚燃料; 中子学; 燃料温度系数

Key words:Th-Pu fuel; Neutronics; Fuel temperature coefficient

基金项目:

中文摘要

采用类似于大亚湾900 MW压水堆的堆芯模型, 使用燃料组件计算程序CASMO4E和反应堆稳态分析程序SIMULATE3分别对铀燃料组件、铀钚燃料组件或钍钚燃料组件组成的堆芯的中子学特性进行了研究, 分析了组件的燃耗深度、堆芯的平均燃耗、燃料温度系数与燃耗的关系. 结果表明, 钍钚燃料组件和铀燃料组件组成的堆芯中子特性相似, 同时钍钚燃料用于焚烧武器级钚时, 具有更高的焚烧效率.

英文摘要

A comparative study of the physics properties of a DAYA BAY like PWR model, with Uranium assembly, U Pu assembly or Th Pu assembly in it, has been made using CASMO4E and SIMULATE3 codes. The parameters such as the exposure of each assembly, the core average exposure, fuel temperature coefficient and its variation as a function of operation period have been investigated. Results show that the neutron properties of Th Pu core and Uranium core are similar, and the Th Pu core can burn numerous weapon grade Pu with higher efficiency.

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