R. Citarella , N. Mantel , F. Penta , M. Perrella , M. Bruno , J.H. You
{"title":"OFHC铜在不同温度下的一次蠕变和二次蠕变","authors":"R. Citarella , N. Mantel , F. Penta , M. Perrella , M. Bruno , J.H. You","doi":"10.1016/j.fusengdes.2025.115144","DOIUrl":null,"url":null,"abstract":"<div><div>The proper design of reliable high temperature structures for the realization of fusion power plants is a key issue. Therefore, the behaviour of primary and secondary creep of involved materials plays a crucial role. Unfortunately, in the case of the oxygen free high conductivity copper (OFHC Cu), employed for manufacturing some parts of the divertor cooling system, a well consolidated creep constitutive model is still missing. In addition, to the authors’ knowledge, only a limited amount of experimental data on the creep of OFHC Cu, obtained at temperatures quite dissimilar from those expected for in service fusion power plants, are available in the literature. In this work the creep behaviour of OFHC Cu in air atmosphere was analysed under different operating conditions. Creep constant-load tests were carried out at 300°C, 400°C, 450°C and 550°C to measure primary and secondary creep strains. The testing load levels were chosen taking account of the creep design aims of the European Demonstration Power Plant (EU-DEMO) project. Finally, phenomenological laws were proposed to model the creep response of the examined material, and numerical analyses on EU-DEMO monoblock component were performed to assess the effect of primary creep response.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115144"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Primary and secondary creep of OFHC copper at various temperatures\",\"authors\":\"R. Citarella , N. Mantel , F. Penta , M. Perrella , M. Bruno , J.H. You\",\"doi\":\"10.1016/j.fusengdes.2025.115144\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The proper design of reliable high temperature structures for the realization of fusion power plants is a key issue. Therefore, the behaviour of primary and secondary creep of involved materials plays a crucial role. Unfortunately, in the case of the oxygen free high conductivity copper (OFHC Cu), employed for manufacturing some parts of the divertor cooling system, a well consolidated creep constitutive model is still missing. In addition, to the authors’ knowledge, only a limited amount of experimental data on the creep of OFHC Cu, obtained at temperatures quite dissimilar from those expected for in service fusion power plants, are available in the literature. In this work the creep behaviour of OFHC Cu in air atmosphere was analysed under different operating conditions. Creep constant-load tests were carried out at 300°C, 400°C, 450°C and 550°C to measure primary and secondary creep strains. The testing load levels were chosen taking account of the creep design aims of the European Demonstration Power Plant (EU-DEMO) project. Finally, phenomenological laws were proposed to model the creep response of the examined material, and numerical analyses on EU-DEMO monoblock component were performed to assess the effect of primary creep response.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"217 \",\"pages\":\"Article 115144\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-03\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625003412\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625003412","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Primary and secondary creep of OFHC copper at various temperatures
The proper design of reliable high temperature structures for the realization of fusion power plants is a key issue. Therefore, the behaviour of primary and secondary creep of involved materials plays a crucial role. Unfortunately, in the case of the oxygen free high conductivity copper (OFHC Cu), employed for manufacturing some parts of the divertor cooling system, a well consolidated creep constitutive model is still missing. In addition, to the authors’ knowledge, only a limited amount of experimental data on the creep of OFHC Cu, obtained at temperatures quite dissimilar from those expected for in service fusion power plants, are available in the literature. In this work the creep behaviour of OFHC Cu in air atmosphere was analysed under different operating conditions. Creep constant-load tests were carried out at 300°C, 400°C, 450°C and 550°C to measure primary and secondary creep strains. The testing load levels were chosen taking account of the creep design aims of the European Demonstration Power Plant (EU-DEMO) project. Finally, phenomenological laws were proposed to model the creep response of the examined material, and numerical analyses on EU-DEMO monoblock component were performed to assess the effect of primary creep response.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.