发布求助
文献互助 智能选刊 最新文献

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy最新文献

筛选
英文 中文
Application of structural-mechanics methods to the design of large tandem-mirror fusion devices (MFTF-B) 结构力学方法在大型串联镜聚变装置设计中的应用
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/0167-899X(86)90007-8
Victor N. Karpenko, Dorothy S. Ng
{"title":"Application of structural-mechanics methods to the design of large tandem-mirror fusion devices (MFTF-B)","authors":"Victor N. Karpenko,&nbsp;Dorothy S. Ng","doi":"10.1016/0167-899X(86)90007-8","DOIUrl":"10.1016/0167-899X(86)90007-8","url":null,"abstract":"<div><p>The Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory requires state-of-the-art structural-mechanics methods to deal with access constraints for plasma heating and diagnostics, alignment requirements, and load complexity and variety. Large interactive structures required an integrated analytical approach to achieve a reasonable level of overall system optimization. The Tandem Magnet Generator (TMG) creates a magnet configuration for the EFFI calculation of electromagnetic-field forces that, coupled with other loads, form the input loading to magnet and vessel finite-element models. The analytical results provide the data base for detailed design of magnet, vessel, foundation, and interaction effects.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"4 1","pages":"Pages 1-10"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(86)90007-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76914897","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Design considerations for the TF coil center conductor post for the Ignition Spherical Torus (IST) 点火球形环面(IST) TF线圈中心导体柱的设计考虑
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80011-8
G.R. Dalton , John R. Haines
{"title":"Design considerations for the TF coil center conductor post for the Ignition Spherical Torus (IST)","authors":"G.R. Dalton ,&nbsp;John R. Haines","doi":"10.1016/S0167-899X(86)80011-8","DOIUrl":"10.1016/S0167-899X(86)80011-8","url":null,"abstract":"<div><p>A trade-off study has been carried out to compare the differential costs of using high-strength alloy copper versus oxygen-free, high-conductivity (OFHC) copper for the center legs of the toroidal field (TF) coils of an Ignition Spherical Torus (IST). The electrical heating, temperatures, stresses, cooling requirements, material costs, pump costs, and power to drive the TF coils and pumps are all assessed for both materials for a range of compact tokamak reactors. The alloy copper material is found to result in a more compact reactor and to allow use of current densities of up to 170 MA/m<sup>2</sup> versus 40 MA/m<sup>2</sup> for the OFHC copper. The OFHC conductor system with high current density is $24 million less expensive than more conventional copper systems with 30 MA/m<sup>2</sup>. The alloy copper system costs $32 million less than conventional systems. Therefore, the alloy system offers a net savings of $8 million compared to the 50% cold-worked OFHC copper system.</p><p>Although the savings are a significant fraction of the center conductor post cost, they are relatively insignificant in terms of the total device cost. It is concluded that the use of alloy copper contributes very little to the economic or technical viability of the compact IST. It is recommended that a similar systematic approach be applied to evaluating coil material and current density trade-offs for other compact copper-TF-coil tokamak designs.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 4","pages":"Pages 409-422"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80011-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87387744","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Mirror advanced reactor study engineering overview 镜像先进反应堆研究工程概述
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/0167-899X(86)90002-9
James D. Gordon
{"title":"Mirror advanced reactor study engineering overview","authors":"James D. Gordon","doi":"10.1016/0167-899X(86)90002-9","DOIUrl":"https://doi.org/10.1016/0167-899X(86)90002-9","url":null,"abstract":"","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 2","pages":"119-150"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(86)90002-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72280370","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Structural mechanics and material aspects of the Next European Torus 下一个欧洲环面的结构力学和材料方面
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80004-0
D.R. Harries, E. Zolti
{"title":"Structural mechanics and material aspects of the Next European Torus","authors":"D.R. Harries,&nbsp;E. Zolti","doi":"10.1016/S0167-899X(86)80004-0","DOIUrl":"10.1016/S0167-899X(86)80004-0","url":null,"abstract":"<div><p>The first wall material problems and the structural mechanics studies being undertaken for the plasma facing components during the current pre-design phase of the Next European Torus (NET) project are described. The activities are aimed at generating the required materials data, setting up qualified analysis tools and criteria, and performing comparative design evaluations, thereby assisting in the final selection of materials and design concepts before embarking on the detailed design of NET at the end of the present decade.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 4","pages":"Pages 331-344"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80004-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88574308","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 10
Numerical analysis of the dynamic response of water-cooled liquid-LiPb breeder blankets to coolant tube rupture 水冷液体- lipb增殖包层对冷却剂管破裂动态响应的数值分析
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80005-2
H.Th. Klippel
{"title":"Numerical analysis of the dynamic response of water-cooled liquid-LiPb breeder blankets to coolant tube rupture","authors":"H.Th. Klippel","doi":"10.1016/S0167-899X(86)80005-2","DOIUrl":"10.1016/S0167-899X(86)80005-2","url":null,"abstract":"<div><p>The dynamic response of different water-cooled liquid Li<sub>17</sub>Pb<sub>83</sub> breeder blanket modules has been calculated to investigate the integrity of these modules under conditions of coolant tube rupture. Numerical calculations with the code PISCES were carried out taking into account the fluid-structure interaction and the elasto-plastic behaviour of the structural material. The results show that for inert coolant characteristics the proposed conceptual designs for INTOR and NET have sufficient resistance against the pressure shock waves created by a coolant tube rupture, but when taking into account energy release due to chemical reaction of water with LiPb-alloy, up to doubling of the wall thickness has to be envisaged to guarantee structural reliability.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 4","pages":"Pages 345-361"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80005-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79327337","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 9
The ignition studies project at princeton 普林斯顿大学的点火研究项目
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80008-8
J.M. Bialek, W. Reiersen, J.C. Citrolo
{"title":"The ignition studies project at princeton","authors":"J.M. Bialek,&nbsp;W. Reiersen,&nbsp;J.C. Citrolo","doi":"10.1016/S0167-899X(86)80008-8","DOIUrl":"10.1016/S0167-899X(86)80008-8","url":null,"abstract":"<div><p>During the past year the Ignition Studies Project (ISP) at Princeton has been investigating design options and performing systems studies on science oriented DT ignition experiments. The goal has been to identify promising approaches leading to a device that could test the basic viability of the burning-plasma regime at a relatively early time and moderate cost. This is a substantial departure from the Tokamak Fusion Core Experiment (TFCX) which had both a physics and an engineering mission. This paper describes some of the approaches under consideration and highlights some of the tradeoffs that need to be understood for the development of an ignition experiment.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 4","pages":"Pages 379-383"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80008-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73695088","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Mirror advanced reactor study (MARS) plasma heating systems 镜像先进反应堆研究（MARS）等离子体加热系统
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/0167-899X(86)90004-2
S.A. Freije, D.M. Goebel
{"title":"Mirror advanced reactor study (MARS) plasma heating systems","authors":"S.A. Freije,&nbsp;D.M. Goebel","doi":"10.1016/0167-899X(86)90004-2","DOIUrl":"https://doi.org/10.1016/0167-899X(86)90004-2","url":null,"abstract":"","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 2","pages":"173-202"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(86)90004-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72280369","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
The ASDEX Upgrade toroidal field magnet and poloidal divertor field coil system adapted to reactor requirements ASDEX Upgrade环向磁场磁体和极向导流器磁场线圈系统适用于反应器的要求
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80017-9
W. Köppendörfer, M. Blaumoser, K. Ennen, J. Gruber, O. Gruber, O. Jandl, M. Kaufmann, H. Kollotzek, H. Kotzlowski, E. Lackner, K. Lackner, T. Von Larcher, J.M. Noterdaeme, M. Pillsticker, R. Pöhlchen, H. Preis, H. Schneider, U. Seidel, B. Sombach, E. Speth, A. Wieczorek
{"title":"The ASDEX Upgrade toroidal field magnet and poloidal divertor field coil system adapted to reactor requirements","authors":"W. Köppendörfer,&nbsp;M. Blaumoser,&nbsp;K. Ennen,&nbsp;J. Gruber,&nbsp;O. Gruber,&nbsp;O. Jandl,&nbsp;M. Kaufmann,&nbsp;H. Kollotzek,&nbsp;H. Kotzlowski,&nbsp;E. Lackner,&nbsp;K. Lackner,&nbsp;T. Von Larcher,&nbsp;J.M. Noterdaeme,&nbsp;M. Pillsticker,&nbsp;R. Pöhlchen,&nbsp;H. Preis,&nbsp;H. Schneider,&nbsp;U. Seidel,&nbsp;B. Sombach,&nbsp;E. Speth,&nbsp;A. Wieczorek","doi":"10.1016/S0167-899X(86)80017-9","DOIUrl":"10.1016/S0167-899X(86)80017-9","url":null,"abstract":"<div><p>ASDEX Upgrade is a tokamak experiment with external poloidal field coils that is now under construction at IPP Garching. It can produce elongated single-null (SN), double-null (DN), and limiter (L) configurations. The SN is the reference configuration with asymmetric load distributions in the poloidal field (PF) system and the toroidal field (TF) magnet. Plasma control and stabilization require a rigid passive conductor close to the plasma. The design principles of the coils and support structure are described.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 3","pages":"Pages 265-272"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80017-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85832910","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 3
Configurational aspects and structural problems of systems integration, maintenance, containment and shielding for next-generation tokamaks (INTOR and NET) 下一代托卡马克(INTOR和NET)系统集成、维护、遏制和屏蔽的配置方面和结构问题
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80009-X
F. Farfaletti-Casali
{"title":"Configurational aspects and structural problems of systems integration, maintenance, containment and shielding for next-generation tokamaks (INTOR and NET)","authors":"F. Farfaletti-Casali","doi":"10.1016/S0167-899X(86)80009-X","DOIUrl":"10.1016/S0167-899X(86)80009-X","url":null,"abstract":"<div><p>The paper reviews the configurational aspects and the structural mechanics of the overall engineering design of next-generation tokamak-type experimental power fusion reactors by describing and analysing two of the present major studies, INTOR and NET. Some safety aspects, related to containment and shielding during operation and maintenance, are also described. INTOR and NET are both considered because they constitute two different, significant approaches to defining the reactor mechanical configuration. The paper introduces the assumptions and the system integration procedures adopted to determine the mechanical configurations. The two designs are described and the structural and engineering problems related to the overall architectural aspects are identified. Finally, the main structural problems and the solution adopted are discussed.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 4","pages":"Pages 385-397"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80009-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89483277","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
Mechanical design assessments of structural components and auxiliaries of the Joint European Torus 联合欧洲环面结构部件和辅助部件的机械设计评估
Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1986-01-01 DOI: 10.1016/S0167-899X(86)80015-5
L. Sonnerup
{"title":"Mechanical design assessments of structural components and auxiliaries of the Joint European Torus","authors":"L. Sonnerup","doi":"10.1016/S0167-899X(86)80015-5","DOIUrl":"10.1016/S0167-899X(86)80015-5","url":null,"abstract":"<div><p>The general design of the Joint European Torus (JET) is briefly described. The loads on its major structural components, at normal operation, and in cases of plasma instability and/or disruption, are discussed. The way these components have been assessed and optimised in relation to their loads is presented. A short account of mechanical design problems of auxiliary equipment is given. Finally, the state of operation of JET and its implications for the mechanical design is summarized.</p><p>The mechanically most important components of the JET device are the support structure of the toroidal magnet, the vacuum vessel, the coils of the magnets and the pedestals supporting the weight of the torus. These components all participate in resisting and transmitting the primary forces during operation.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"3 3","pages":"Pages 233-247"},"PeriodicalIF":0.0,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0167-899X(86)80015-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76026460","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 4
首页 上一页 下一页 尾页
0
×
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
请完成安全验证×
相关产品
×
本文献相关产品
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 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号：481959085
Book学术官方微信