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 Recent Contributions to Physics Pub Date : 2023-09-01 DOI:10.26577/rcph.2023.v86.i3.05
Ye.V. Chikhray
{"title":"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","authors":"Ye.V. Chikhray","doi":"10.26577/rcph.2023.v86.i3.05","DOIUrl":null,"url":null,"abstract":"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.","PeriodicalId":29678,"journal":{"name":"Recent Contributions to Physics","volume":null,"pages":null},"PeriodicalIF":0.2000,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Calculation of thermomechanical stresses and deformations in a reactor ampoule device with lithium ceramics under neutron irradiation\",\"authors\":\"Ye.V. Chikhray\",\"doi\":\"10.26577/rcph.2023.v86.i3.05\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"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.\",\"PeriodicalId\":29678,\"journal\":{\"name\":\"Recent Contributions to Physics\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.2000,\"publicationDate\":\"2023-09-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Recent Contributions to Physics\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.26577/rcph.2023.v86.i3.05\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"PHYSICS, MULTIDISCIPLINARY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Recent Contributions to Physics","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.26577/rcph.2023.v86.i3.05","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"PHYSICS, MULTIDISCIPLINARY","Score":null,"Total":0}
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。
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
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.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
自引率
0.00%
发文量
0
期刊最新文献
Installation and technique of experimental investigations of composite materials based on beryllium Calculation of thermomechanical stresses and deformations in a reactor ampoule device with lithium ceramics under neutron irradiation Physical fields as factors of natural processes in the works of the center for astrophysical research of North Kazakhstan University Simulation of atomization and ignition of high-pressure jet stream Development and synchronization of semiconductors excitation sources for active elements on self-terminatint transitions in metal vapors
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1