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Analyses Of A Restrained Growth Graphite Irradiation Creep Experiment

机译:抑制生长石墨辐照蠕变实验的分析

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Graphite is used as a moderator, reflector and structural component in pebble bed and prism High Temperature Reactors (HTRs). It is fortunate to reactor designers that irradiated graphite shows remarkably high creep behaviour under the influence of fast neutron irradiation at temperatures far below those required for significant creep strains to be generated in unirradiated graphite. This creep behaviour is important in the design of nuclear graphite reactor cores because the self-induced shrinkage stresses generated in typical core components during irradiation can be relieved. However, there are no reliable data on high fluence irradiation creep and the mechanistic understanding of the irradiation creep is insufficiently developed to reliably extrapolate to the high fluences expected of graphite in future HTR designs. The understanding of irradiation creep is further complicated because it has been experimentally observed that irradiation creep strain in graphite modifies other properties in particular the coefficient of thermal expansion. In addition modified changes in Young's modulus in crept specimens have been reported and it has also been postulated that irradiation creep may also modify dimensional change. The assessment of irradiation creep in graphite components is based on empirical laws derived from data obtained from small samples irradiated in a materials test reactor. However, due to the complicated irradiation rigs required and the amount of dimensional and property measurements needed to be taken, constant stress irradiation creep experiments are difficult and very expensive to carry out successfully. However, restrained creep experiments are simple to implement, less expensive and can be easily included as part of other, more conventional irradiation graphite experimental programmes. However, in the past, the disadvantage of these experiments has been that the results have been difficult to interpret using the then available analytical methods. In this paper the restrained creep experiment is revisited and analysed numerically and the possible benefit of using a restrained creep experiment in future graphite irradiation experiments is investigated. It is shown that a numerical simulation of the restrained creep experiment behaviour would be an essential tool to ensure that the stress within the specimen remains within defined limits so that specimen failure can be avoided.
机译:石墨在卵石床和棱镜高温反应器(HTR)中用作调节剂,反射器和结构部件。对于反应堆设计者来说幸运的是,在远低于未辐照石墨中产生显着蠕变应变所需温度的温度下,在快速中子辐照的影响下,辐照石墨显示出非常高的蠕变行为。这种蠕变行为在核石墨反应堆堆芯的设计中很重要,因为可以缓解辐射过程中典型堆芯组件中产生的自感应收缩应力。但是,没有关于高通量辐照蠕变的可靠数据,并且对辐照蠕变的机理的理解还不足以可靠地推断未来HTR设计中石墨所期望的高通量。对辐射蠕变的理解更加复杂,因为已经通过实验观察到石墨中的辐射蠕变应变会改变其他特性,特别是热膨胀系数。此外,据报道,蠕变样品的杨氏模量发生了变化,据推测辐照蠕变也可能改变尺寸变化。石墨组分中辐射蠕变的评估是基于经验法则,该经验法则是从材料测试反应器中辐照的小样品获得的数据得出的。但是,由于需要复杂的辐照设备,并且需要进行大量的尺寸和性能测量,因此恒应力辐照蠕变实验难以成功进行,而且非常昂贵。但是,受约束的蠕变实验易于实施,成本较低,并且可以容易地包含在其他更常规的辐射石墨实验程序中。然而,过去,这些实验的缺点是难以用当时可用的分析方法来解释结果。本文对约束蠕变实验进行了重新讨论并进行了数值分析,并研究了在未来的石墨辐照实验中使用约束蠕变实验的可能益处。结果表明,有限蠕变实验行为的数值模拟将是确保标本内应力保持在限定范围内的必要工具,从而可以避免标本破坏。

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