首页> 外文会议>International congress on advances in nuclear power plants >THE REDISTRIBUTION OF FORCES IN A PEBBLE BED REACTOR DUE TO RADIATION INDUCED PEBBLE SHRINKAGE AND OTHER PROPERTY CHANGES
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THE REDISTRIBUTION OF FORCES IN A PEBBLE BED REACTOR DUE TO RADIATION INDUCED PEBBLE SHRINKAGE AND OTHER PROPERTY CHANGES

机译:由于辐射引起的卵形收缩和其他性能变化,卵形床反应器中的力分布

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The pebble bed reactor (PBR) is generation IV reactor design that is highly efficient and passively safe. The core of a PBR consists of a silo full of graphite pebbles filled with tristructural-isotropic fuel. This fuel acts as both a moderator and radiation isotope containment preventing the release of fission biproducts. The fuel elements are first piled in the core until criticality is reached. As burnup occur, the fuel elements are recycled from the bottom of the core and replaced at the top of the core. With each pass the fuel is measured for burnup. If it is below the burnup limit, and has not received significant structural damage, it is recycled. If not, it will be placed directly in diy casks for storage. Because of its inert nature, there is no need for cutting or processing before storage. A fuel element is designed to stay in the core for roughly 3 years. Both the fuel elements, and core structure material are composed mostly of graphite. This graphite will experience significant property changes based on both the thermal expansion, and the neutron irradiation. These changes include the Young's modulus, Poisson's ratio, density and swelling, and coefficient of thermal conductivity. The effects of irradiation on the core structure material, and the resulting core behavior, has been well studied. Previously the effect of dynamic properties of the graphite fuel pebbles due to irradiation has been assumed negligible. With advances in computing power, it has become feasible to model graphite fuel element property changes and their effect on the core geometry and maximum pebble temperatures. This modelling can be accomplished using the discrete element method (DEM). In this paper the discrete element method is described. Previous research on graphite property changes based on temperature and irradiation dose is summarized. This previous research was used to augment the discrete element method with dynamic graphite pebble properties. The core was simulated over a three-year period with graphite pebble property changes. In this study the forces are examined. It was shown that the dynamic property changes lead to unsafe changes in pebble forces. These estimates are consistent with previous reactors and show that dynamic property changes could be better used to model the PBR core.
机译:卵石床反应器(PBR)是第四代反应器设计,具有高效和被动安全性。 PBR的核心由充满石墨鹅卵石的筒仓组成,里面充满了三向同性燃料。该燃料既充当减速剂,又充当放射性同位素的容器,可防止裂变副产物的释放。首先将燃料元件堆放在堆芯中,直到达到临界状态为止。当发生燃尽时,燃料元件从堆芯的底部再循环并在堆芯的顶部更换。每次通过都会测量燃料的燃耗。如果它低于燃尽极限,并且没有受到重大的结构损坏,则将其回收。如果没有,它将直接放置在diy桶中进行存储。由于其惰性,因此无需在储存前进行切割或加工。燃料元件设计为可在堆芯中停留大约3年。燃料元件和芯结构材料都主要由石墨组成。基于热膨胀和中子辐照,该石墨将经历显着的性能变化。这些变化包括杨氏模量,泊松比,密度和溶胀以及导热系数。辐射对核心结构材料的影响以及由此产生的核心行为已得到了很好的研究。以前,已经假定由于辐照引起的石墨燃料小石的动态特性的影响可以忽略不计。随着计算能力的提高,对石墨燃料元件特性变化及其对堆芯几何形状和最大卵石温度的影响进行建模已变得可行。可以使用离散元素方法(DEM)来完成此建模。本文描述了离散元法。总结了基于温度和辐照剂量对石墨性能变化的研究。先前的研究被用来增强具有动态石墨卵石特性的离散元方法。在三年的时间内对岩心进行了模拟,石墨的卵石特性发生了变化。在这项研究中,检查了力。结果表明,动态特性的变化会导致卵石力的不安全变化。这些估计值与以前的反应堆一致,表明动态特性变化可以更好地用于模拟PBR堆芯。

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