wwer - 440型核反应堆压力容器内部材料的热退火

Ivana Schnablová, R. Kopřiva, Ondřej Buršík, K. Rusňáková, A. Materna
{"title":"wwer - 440型核反应堆压力容器内部材料的热退火","authors":"Ivana Schnablová, R. Kopřiva, Ondřej Buršík, K. Rusňáková, A. Materna","doi":"10.37904/metal.2020.3497","DOIUrl":null,"url":null,"abstract":"Current trend of long-term operation of NPP’s for more than 60 years requires assurance of its safety and reliability. One of the solutions how to extend service life of reactor pressure vessel (RPV) is thermal annealing, which became a verified technology and its application in nuclear industry was prompted mainly due to an inability of RPV exchange. At present time, there is no comparable method for RPV internals that are not monitored by surveillance program and their material is exposed to significantly more intense neutron flux than the RPV. Paper presents the thermal annealing as one of the possible solutions to provide and re-establish sufficient mechanical properties of RPV internals during the operation. According to previously obtained results of unirradiated material, two thermal annealing regimes for irradiated experimental material were selected based on the annealing temperatures of 550 and 600 °C. The possibility of recovery of mechanical properties to the level almost corresponding to the initial state by the thermal annealing was studied by hardness testing and static fracture toughness tests before and after the thermal annealing of irradiated material.","PeriodicalId":21337,"journal":{"name":"Revue De Metallurgie-cahiers D Informations Techniques","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"THERMAL ANNEALING OF WWER – 440 NUCLEAR REACTOR PRESSURE VESSEL INTERNALS MATERIAL\",\"authors\":\"Ivana Schnablová, R. Kopřiva, Ondřej Buršík, K. Rusňáková, A. Materna\",\"doi\":\"10.37904/metal.2020.3497\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Current trend of long-term operation of NPP’s for more than 60 years requires assurance of its safety and reliability. One of the solutions how to extend service life of reactor pressure vessel (RPV) is thermal annealing, which became a verified technology and its application in nuclear industry was prompted mainly due to an inability of RPV exchange. At present time, there is no comparable method for RPV internals that are not monitored by surveillance program and their material is exposed to significantly more intense neutron flux than the RPV. Paper presents the thermal annealing as one of the possible solutions to provide and re-establish sufficient mechanical properties of RPV internals during the operation. According to previously obtained results of unirradiated material, two thermal annealing regimes for irradiated experimental material were selected based on the annealing temperatures of 550 and 600 °C. The possibility of recovery of mechanical properties to the level almost corresponding to the initial state by the thermal annealing was studied by hardness testing and static fracture toughness tests before and after the thermal annealing of irradiated material.\",\"PeriodicalId\":21337,\"journal\":{\"name\":\"Revue De Metallurgie-cahiers D Informations Techniques\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2020-01-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Revue De Metallurgie-cahiers D Informations Techniques\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.37904/metal.2020.3497\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Revue De Metallurgie-cahiers D Informations Techniques","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.37904/metal.2020.3497","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

摘要

核电站长期运行超过60年的趋势要求保证其安全性和可靠性。延长反应堆压力容器(RPV)使用寿命的解决方案之一是热退火技术,该技术已得到验证,其在核工业中的应用主要是由于RPV无法交换。目前,对于不受监测程序监测的RPV内部,没有可比较的方法,它们的材料暴露在比RPV更强的中子通量中。本文提出了热退火作为一种可能的解决方案,以提供和重新建立足够的机械性能的RPV内部在操作过程中。根据已有的未辐照材料的结果,选择了两种退火方案,退火温度分别为550℃和600℃。通过对辐照材料进行热处理前后的硬度测试和静态断裂韧性测试,研究了热处理使材料的力学性能恢复到几乎与初始状态相对应的水平的可能性。
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
THERMAL ANNEALING OF WWER – 440 NUCLEAR REACTOR PRESSURE VESSEL INTERNALS MATERIAL
Current trend of long-term operation of NPP’s for more than 60 years requires assurance of its safety and reliability. One of the solutions how to extend service life of reactor pressure vessel (RPV) is thermal annealing, which became a verified technology and its application in nuclear industry was prompted mainly due to an inability of RPV exchange. At present time, there is no comparable method for RPV internals that are not monitored by surveillance program and their material is exposed to significantly more intense neutron flux than the RPV. Paper presents the thermal annealing as one of the possible solutions to provide and re-establish sufficient mechanical properties of RPV internals during the operation. According to previously obtained results of unirradiated material, two thermal annealing regimes for irradiated experimental material were selected based on the annealing temperatures of 550 and 600 °C. The possibility of recovery of mechanical properties to the level almost corresponding to the initial state by the thermal annealing was studied by hardness testing and static fracture toughness tests before and after the thermal annealing of irradiated material.
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
审稿时长
24 months
期刊最新文献
Preparation and performance analysis of gas-quenched steel slag beads Abnormal toughness characteristics and fracture model in simulated welding HAZ of 5%Ni Steel Measurement of the steady state tearing in thin sheets using the contactless system Evaluation of carbothermic processing for mixed discarded lithium-ion batteries Influence of Nb2O5 and basicity on the viscosity and structure of CaO-SiO2-Nb2O5-CeO2-CaF2 slag system
×
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