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首页> 外文期刊>Journal of nuclear engineering and radiation science >Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
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Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

机译:高温反应器HTR-PM中移动鹅卵石的统计燃烧分布

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摘要

In the pebble-bed high-temperature reactor under construction in China, called the HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. The burnup of each pebble is checked at the core outlet and, according to the achieved burnup level, the pebble might be disposed or reinserted into the upper section of the core. Upon reinsertion, each pebble is radially distributed in a random manner and, according to its downward path, faces different burnup conditions. Hence, the number of passes necessary to achieve the average discharge burnup of 90 MWd/kgU may vary. Discrete element method (DEM) simulations have been carried out to achieve a clear understanding of the movement of the 420000 fuel pebbles in the HTR-PM core. At the same time, neutronics properties have been investigated for a single pebble and for the full core with the Serpent 2 Monte Carlo code. As a result, one-group microscopic cross sections (XS) have been parametrized at the core level. The pebble movement has been loosely coupled with the depletion of a single pebble in a dedicated burnup script called moving pebble burnup (MPB), developed in MATLAB. 3000 single pebble burnup histories were simulated to obtain sufficient statistics and an insight into the HTR-PM burnup process. The decrease of the average burnup gained per single pass implies that a misshandling of recirculated fuel elements is unlikely to lead to an excess of the maximum allowed burnup of 100 MWd/kgU. The core demonstrates a self-compensation effect of burnup, meaning that it always compensates burnup under- or over-runs in the successive passes. In addition, gamma detection of Cs-137 has been studied as a practical method for monitoring the burnup of the discharged pebbles, turning out to be an applicable measurement technique. Finally, it is possible to conclude that the fuel cycle of the HTR-PM, as it has been laid out, is well designed and feasible.
机译:在中国正在建设的球床高温反应堆HTR-PM中,球形燃料元件在圆柱形堆芯中不断向下流动。在堆芯出口检查每个卵石的燃耗,根据达到的燃耗水平,可以将卵石处理或重新插入堆芯上部。重新插入后,每个卵石以随机方式呈径向分布,并且根据其向下路径,面临不同的燃耗条件。因此,实现90 MWd/kgU平均放电燃耗所需的焊道数可能会有所不同。为了清楚地了解HTR-PM堆芯中42万个燃料卵石的运动,已经进行了离散元法(DEM)模拟。同时,用蛇2蒙特卡罗程序研究了单个卵石和整个堆芯的中子学性质。因此,一组显微横截面(XS)已在核心层面参数化。在MATLAB中开发的一个名为移动卵石燃耗(MPB)的专用燃耗脚本中,卵石的移动与单个卵石的耗尽是松散耦合的。为了获得足够的统计数据和对HTR-PM燃耗过程的深入了解,模拟了3000个单卵石燃耗历史。单道次获得的平均燃耗降低意味着再循环燃料元件的误操作不太可能导致超过100 MWd/kgU的最大允许燃耗。堆芯显示出燃耗的自我补偿效应,这意味着它总是补偿连续焊道中的不足或过度燃耗。此外,还研究了铯-137的伽马探测,作为监测排放卵石燃耗的实用方法,结果证明是一种适用的测量技术。最后,可以得出这样的结论:HTR-PM的燃料循环设计良好,可行。

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