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_第9页

Inelastic structural analysis of the mars tandem mirror reactor 火星串联反射堆的非弹性结构分析

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90003-5

J.P. Blanchard, N.M. Ghoniem

{"title":"Inelastic structural analysis of the mars tandem mirror reactor","authors":"J.P. Blanchard, N.M. Ghoniem","doi":"10.1016/0167-899X(85)90003-5","DOIUrl":"10.1016/0167-899X(85)90003-5","url":null,"abstract":"<div><p>The effects of radiation on the structural performance of fusion reactor structures is recognized as a major issue for the development of fusion reactor technology. Neutron irradiation changes the mechanical properties of structural components resulting in a general degradation of these properties. In addition to the mechanical loads (pressure and weight) and the thermal strains, non-uniform inelastic strain fields are induced by radiation swelling and creep in fusion structures. In this paper, we describe a new computer code, STAIRE, for <span><math><mtext>ST</mtext></math></span>ress <span><math><mtext>A</mtext></math></span>nalysis <span><math><mtext>I</mtext></math></span>ncluding <span><math><mtext>R</mtext></math></span>adiation <span><math><mtext>E</mtext></math></span>ffects. This code is based on standard beam theory for pipe-bends. The theory is modified in two areas: (1) consideration of the pipes' cross-section deformation as the radius of curvature changes; and (2) inclusion of inelastic radiation and thermal strains (swelling and creep). An efficient analytical/numerical approach is developed for the solution of indeterminate beam problems. As an application of the method, the stress distribution and deflections of toroidal blanket pipes in the Mirror Advanced Reactor Study (MARS) are evaluated. Swelling strains are identified as a major source of stress and deformation in the proposed blanket design, and possible solutions to the problem are outlined.</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":"2 1","pages":"Pages 19-27"},"PeriodicalIF":0.0,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(85)90003-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80248013","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

Methods for forecasting performance limits of fusion reactor structural materials 核聚变反应堆结构材料性能极限预测方法

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90009-6

G.E. Lucas, G.R. Odette

{"title":"Methods for forecasting performance limits of fusion reactor structural materials","authors":"G.E. Lucas, G.R. Odette","doi":"10.1016/0167-899X(85)90009-6","DOIUrl":"10.1016/0167-899X(85)90009-6","url":null,"abstract":"<div><p>For the purposes of both developing appropriate alloys for fusion reactors and ultimately designing and building such devices, it is necessary to determine the mechanical response to high energy neutron irradiation of candidate structural materials. The current and near-term facilities for providing the requisite testing environment are either limited by dissimilarity to fusion reactor environments (i.e., fission reactors), or irradiation volume, or both. This necessitates the development of both a testing technology commensurate with the available facilities — i.e., primarily small specimen technology — and a correlation methodology which recognizes the limitations of the anticipated data base and maximizes the use of that data. In this paper we (1) describe a general philosophy for such correlation methodologies, (2) provide a brief overview of small specimen test techniques and data characteristics, and (3) demonstrate with several examples how correlations can be developed and applied.</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":"2 1","pages":"Pages 145-173"},"PeriodicalIF":0.0,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(85)90009-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88869883","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: 11

TASKA-M — a low cost technology test tandem mirror TASKA-M -低成本技术测试串联反射镜

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90015-1

G. Emmert

引用次数: 3

Effect of plasma motion in disruption on the electromagnetic behavior of a vacuum vessel 等离子体运动对真空容器电磁特性的影响

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90035-7

Kimihiro Ioki, Setsuo Niikura, Katsuo Namiki, Fushiki Matsuoka

引用次数: 8

Author index to volume 2 第二卷的作者索引

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90029-1

引用次数: 0

A comparison of pulsed and steady-state tokamak reactor burn cycles. Part II: Magnet fatigue, power supplies, and cost analysis 脉冲和稳态托卡马克反应堆燃烧循环的比较。第二部分:磁铁疲劳、电源和成本分析

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90021-7

D.A. Ehst, J.N. Brooks, K. Evans Jr., S. Kim

{"title":"A comparison of pulsed and steady-state tokamak reactor burn cycles. Part II: Magnet fatigue, power supplies, and cost analysis","authors":"D.A. Ehst, J.N. Brooks, K. Evans Jr., S. Kim","doi":"10.1016/0167-899X(85)90021-7","DOIUrl":"10.1016/0167-899X(85)90021-7","url":null,"abstract":"<div><p>Pulsed operation of a tokamak reactor imposes cost penalties due to such problems as mechanical fatigue and the need to periodically transfer large amounts of energy to various reactor components. This study focuses on lifetime limitations and capital costs of reactor subsystems in an attempt to quantify sensitivity to pulsed operation. Major problem areas include: fatigue in pulsed poloidal field coils; out-of-plane bending fatigue in toroidal field coils; electric power supply costs; and noninductive current driver costs. A capital cost comparison is made for tokamak reactors operating under the four distinct operating cycles which have been proposed. Since high availability and a low cost of energy will be mandatory for a commercial fusion reactor, we can characterize improvements in physics and technology which will help achieve these goals for different burn cycles. A key conclusion is that steady-state operation is likely to result in the least expensive tokamak reactor (perhaps 20% cheaper than the best pulsed reactor), provided noninductive current drive efficiency can be increased roughly four-fold over present-day experimental results.</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":"2 3","pages":"Pages 319-336"},"PeriodicalIF":0.0,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(85)90021-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72435851","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: 23

Helium effects on the creep and fatigue resistance of austenitic stainless steels at high temperatures 氦对奥氏体不锈钢高温蠕变和抗疲劳性能的影响

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90006-0

Herbert Schroeder, Wilto Kesternich, Hans Ullmaier

引用次数: 73

Reduction of the cyclic stress fatigue due to the over-turning force on the toroidal field coils by quasi-steady operation in a tokamak fusion reactor 托卡马克聚变反应堆准稳态运行对环形场线圈倾覆力引起的循环应力疲劳的减小

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90034-5

Satoshi Nishio, Masayoshi Sugihara

引用次数: 0

A comparison of the key features of tandem mirror technology test facilities 串列反射镜技术试验装置的主要特点比较

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90012-6

P. Komarek, G.L. Kulcinski

引用次数: 5

Optimization of the plasma startup scenario for the RF current drive tokamak by calculus of variations 用变分法优化射频电流驱动托卡马克等离子体启动方案

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1985-01-01 DOI: 10.1016/0167-899X(85)90036-9

Takashi Okazaki , Masayoshi Sugihara, Satoshi Nishio, Noboru Fujisawa

引用次数: 2