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

Liquid metal condensation in the cavity of the HIBALL heavy ion fusion reactor HIBALL重离子聚变反应堆腔内液态金属的冷凝

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90033-3

L. Pong, M.L. Corradini, R.R. Peterson, G.A. Moses

{"title":"Liquid metal condensation in the cavity of the HIBALL heavy ion fusion reactor","authors":"L. Pong, M.L. Corradini, R.R. Peterson, G.A. Moses","doi":"10.1016/0167-899X(85)90033-3","DOIUrl":"10.1016/0167-899X(85)90033-3","url":null,"abstract":"<div><p>In the HIBALL heavy ion beam fusion reactor design, the INPORT concept is used to protect the first surface of the reactor from damage by the high energy X-rays, ion debris and fast neutrons from the exploding target. Liquid Li<sub>17</sub>Pb<sub>83</sub> flows through porous SiC tubes and wets outside of the tubes with a layer of Li<sub>17</sub>Pb<sub>83</sub>. This Li<sub>17</sub>Pb<sub>83</sub> film is evaporated on each shot by the target X-rays and ion debris. The mechanisms that control the vapor pressure of the chamber are: gas radiation, Li<sub>17</sub>Pb<sub>83</sub> evaporation from the INPORT tubes, and gas condensation back onto the INPORT tubes. From the beam stripping cross section for Bi<sup>2+</sup> ions on Pb the gas pressure (evaluated at 0°C) inside the chamber must be at or below 10<sup>−4</sup> torr in order for the ion beam to reach the target and ignite it. The repetition rate is therefore determined by the time required to reestablish this pressure after a shot. Calculations are presented that indicate that this time is short enough to allow a 5 Hz repetition rate for a wide range of parameters.</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 1","pages":"Pages 47-57"},"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)90033-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77206788","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

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90029-1

引用次数: 0

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

On the economics of fissile breeding alternatives 关于裂变育种替代方案的经济学

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90038-2

Stefan Taczanowski

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 Epub Date: 2004-08-26 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

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 Epub Date: 2004-09-07 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

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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90034-5

Satoshi Nishio, Masayoshi Sugihara

引用次数: 0

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 Epub Date: 2004-08-26 DOI: 10.1016/0167-899X(85)90006-0

Herbert Schroeder, Wilto Kesternich, Hans Ullmaier

引用次数: 73

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. 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 Epub Date: 2004-09-07 DOI: 10.1016/0167-899X(85)90036-9

Takashi Okazaki , Masayoshi Sugihara, Satoshi Nishio, Noboru Fujisawa

引用次数: 2