双面慢化环形燃料反应堆物理实验

Critical Experiment of Double-sided Moderator Annular Fuel Reactor

  • 摘要: 环形燃料零功率反应堆是首个双面慢化环形燃料作为核燃料的反应堆。本文采用周期法、落棒法获取环形燃料零功率反应堆的临界参数、控制棒价值、元件价值、含Gd元件的反应性效应等关键参数,对环形燃料零功率反应堆的物理性能进行实验研究,验证环形燃料反应堆堆芯物理设计计算程序。结果表明:根据外推过程确定堆芯临界装载环形燃料元件96根,实心燃料元件172根,此时keff为1.000 40,堆芯调节棒价值为-247.5 pcm,安全棒价值为-1 358.4 pcm;元件价值与理论值平均偏差为1.3 pcm,含Gd元件反应性效应与理论值平均相对偏差为8.8%。本文结果为环形燃料的工程化设计程序提供关键数据支撑。

     

    Abstract: The annular fuel zero power reactor is the first reactor to use double-sided moderator annular fuel as nuclear fuel. In this research, the period method and the drop rod method were used to obtain the critical parameters of the annular fuel zero power reactor, the worth of the control rod, the fuel cell worth, the reactivity effect of the Gd-containing cell and other critical parameters. The physical performance of the annular fuel zero power reactor was experimentally studied, which verified the core physical code for the annular fuel reactor. The results show that the core is loaded with 96 annular fuel cells and 172 solid fuel cells according to the extrapolation critical process. At this time, the keff is 1.000 40, the worth of the regulating rod is -247.5 pcm, and the worth of the safety rod is -1 358.4 pcm. The average deviation of the fuel cell from the theoretical worth is 1.3 pcm, and the average deviation of the Gd-containing cell reactivity effect from the theoretical worth is 8.8%. These experimental data provide critical data support for the annular fuel core physical engineering design code.

     

/

返回文章
返回