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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

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The development of a program system for the design of superconducting poloidal field coils 超导极向磁场线圈设计程序系统的开发
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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(86)90008-X
S. Tado, T. Narikawa, H. Tomita, S. Yamaguchi, T. Tsukamoto, K. Ueda, T. Yamada, T. Fukunaga, T. Satow, T. Ichihara, O. Asai, Y. Hattori, S. Sakabe, B. Ikeda
{"title":"The development of a program system for the design of superconducting poloidal field coils","authors":"S. Tado,&nbsp;T. Narikawa,&nbsp;H. Tomita,&nbsp;S. Yamaguchi,&nbsp;T. Tsukamoto,&nbsp;K. Ueda,&nbsp;T. Yamada,&nbsp;T. Fukunaga,&nbsp;T. Satow,&nbsp;T. Ichihara,&nbsp;O. Asai,&nbsp;Y. Hattori,&nbsp;S. Sakabe,&nbsp;B. Ikeda","doi":"10.1016/0167-899X(86)90008-X","DOIUrl":"10.1016/0167-899X(86)90008-X","url":null,"abstract":"<div><p>A program system was developed for the purpose of the computer aided design of superconducting poloidal field coils in tokamak fusion devices. The program system consists of a main program, twelve subroutines and three data files. The main program effects the initialization of the program system and subsequent control of the calculation process. The system can be operated both in iterative mode and batch one by modifying it. The subroutines perform the calculation of electromagnetic variables, the structural design of the coils and the estimation of their design solutions. The data files play the role of a data base.</p><p>The program system greatly reduces the large amount of labor and time required to design superconducting poloidal field coils. Utilizing the data files, users can readily redesign any part of the coils.</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 11-19"},"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)90008-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80033385","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
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 Epub Date: 2005-10-14 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 Epub Date: 2004-09-07 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 Epub Date: 2005-10-14 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 Epub Date: 2005-10-14 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
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 Epub Date: 2004-09-07 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 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 Epub Date: 2005-10-14 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
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 Epub Date: 2005-10-14 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
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 Epub Date: 2005-10-14 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
Author index to volume 3 第三卷的作者索引
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 Epub Date: 2005-10-14 DOI: 10.1016/S0167-899X(86)80013-1
{"title":"Author index to volume 3","authors":"","doi":"10.1016/S0167-899X(86)80013-1","DOIUrl":"https://doi.org/10.1016/S0167-899X(86)80013-1","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 4","pages":"Pages 425-426"},"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)80013-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"137257926","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
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