中子辐照下锂陶瓷反应器安瓿装置的热力学应力和变形计算

IF 0.2 Q4 PHYSICS, MULTIDISCIPLINARY
Ye.V. Chikhray
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引用次数: 0

摘要

在同时暴露于中子和伽马辐射、气体环境和热负荷的条件下,反应堆实验仍然是评估聚变反应堆中有前途的功能材料性能的少数可用方法之一。中子辐照试验结合数值模拟(有限元法)的应用,可以通过将填充物的宏观响应与单个卵石的微观相互作用联系起来,从而全面了解卵石充填层的复杂力学行为。本文的目的是描述在WWR-K反应堆(阿拉木图,哈萨克斯坦)辐照期间放置陶瓷样品的陶瓷球的球床和辐照装置外壳中发生的热机械应力和变形的建模过程和结果。计算结果表明,在wwrk - k辐照装置的胶囊内密集填充陶瓷卵石,使其无法在填料内移动,当加热到1073K时,将承受10 ~ 80MPa的热机械载荷,超过陶瓷Li4SiO4的极限强度60MPa。超过抗拉强度的卵石所占的份额将从其总数的5%到10%不等。在这种情况下,在连接胶囊与安装法兰的钢制真空管的热伸长的影响下,胶囊将向下移动1-2mm,并径向膨胀200微米。管子的强度不会受到影响。在一定的外部压力下,鹅卵石会突然移动(“跳”)到卵石床上方的空白区域,减少了对剩余鹅卵石的压力。在这个模型的框架内描述这样的行为是不可能的。上述计算与中子辐照下锂陶瓷球床压实的情况有关。避免陶瓷卵石潜在破坏的一种可能方法是将胶囊壁的厚度降低2-3倍,这样会导致胶囊壁的塑性增加,使球床上的壁压降低,使胶囊和陶瓷的加热温度降低。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Calculation of thermomechanical stresses and deformations in a reactor ampoule device with lithium ceramics under neutron irradiation
Reactor experiments remain one of the few available methods for evaluating the performance of promising functional materials for fusion reactors under conditions of simultaneous exposure to neutron and gamma radiation, a gaseous environment, and thermal loads. Testing under neutron irradiation together with the application of numerical simulations (Finite Element Method) can lead to a complete understanding of the complex mechanical behavior of packed layers of pebbles by relating the macroscopic response of the infill to the microscopic interactions in a single pebble. The objective of this paper is describing the procedure and results of modeling of thermomechanical stresses and deformations that occur in the pebble bed of ceramic balls and in the irradiation device housing, in which the studied ceramic samples are placed during irradiation at the WWR-K reactor (Almaty, Kazakhstan). Calculation results show that ceramic pebbles, densely filled into the capsule of the WWR-K irradiation device so that they cannot move inside the filling, when heated to 1073K, will undergo thermomechanical loads from 10 to 80MPa, which exceeds the ultimate strength of 60MPa of ceramics Li4SiO4. The share of pebbles, the load on which exceeds the tensile strength, will be from 5 to 10% of their total number. In this case, the capsule will move down by 1-2mm, and expand by 200 microns radially under the influence of thermal elongation of the steel vacuum tubes connecting the capsule to the mounting flange. The strength of the tubes will not be affected. At a certain value of external pressure, the pebbles will abruptly move ("jump") into the empty area above the pebble bed, reducing the pressure on the remaining pebbles. It is not possible to describe such behavior within the framework of this model. The above calculations are relevant for the case of compacted pebble bed of lithium ceramics under neutron irradiation. A possible way to avoid the potential destruction of ceramic pebbles is to reduce the thickness of the capsule wall by 2-3 times, which will lead to an increase in the plasticity of the capsule walls, a decrease in the wall pressure on the pebble bed, and a decrease in the heating temperature of the capsule and ceramics.
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