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CNP1500核电站堆芯燃料管理研究

Study on In-core Fuel Management for CNP1500 Nuclear Power Plant(In Chinese)

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【作者】 李冬生

【Author】 LI Dongsheng(National Key Lab.of Reactor System Design Technology,Nuclear Power Institute of China,Chengdu,610041)

【机构】 中国核动力研究设计院核反应堆系统设计技术国家级重点实验室 成都610041

【摘要】 CNP1500是四环路、轻水慢化和冷却的压水堆核电站,反应堆堆芯由205个AFA-3GXL燃料组件组成,堆芯冷态活性段高度为426.7 cm,等效直径为347.0 cm。反应堆热功率输出为4 250 MW,平均线功率密度为179.5 W/cm。平衡循环堆芯的循环长度为470有效满功率天,各循环堆芯所有状态下的慢化剂温度系数均为负值;各循环热态满功率、无控制棒、平衡氙状态下的核焓升因子FΔH都低于限值;最大卸料组件燃耗小于55 000 MW.d/tU;各循环寿期末停堆裕量满足设计准则;低泄漏堆芯装载降低了反应堆压力容器的辐照损伤,有利于延长压力容器的使用寿命。叙述了CNP1500核电站堆芯燃料管理设计方案及主要计算结果。

【Abstract】 CNP1500 is a four-loop PWR nuclear power plant with light water as moderator and coolant.The reactor core is composed of 205 AFA-3GXL fuel assemblies.The active core height at cold is 426.4 cm and equivalent diameter is 347.0 cm.The reactor thermal output is 4 250 MW,and average linear power density is 179.5 W/cm.The cycle length of equilibrium cycle core is 470 equivalent full power days.For all cycles,the moderator temperature coefficients at all conditions are negative values,the nuclear enthalpy rise factors FΔH at hot full power,all control rods out and equilibrium xenon are less than the limit value,the maximum discharge assembly burnup is less 55 000 MW·d/tU,and the shutdown margin values at the end of life meet design criteria.The low-leakage core loading reduces radiation damage on pressure vessel and is beneficial to prolong use lifetime of it.The in-core fuel management design scheme and main calculation results for CNP1500 nuclear power plant are presented.

  • 【文献出处】 中国核科技报告 ,China Nuclear Science and Technology Report , 编辑部邮箱 ,2005年01期
  • 【分类号】TL384
  • 【下载频次】103
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