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

2.1. Development of low activation Al alloys for the R-project 2.1. r -工程低活化铝合金的研制

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90019-X

Kohji Kamada

引用次数: 3

Preliminary surveillance of prospective site — environmental considerations — 对未来选址的初步监测。环境考虑

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90027-9

H. Obayashi , H. Amano , K. Komura , Y. Sakuma , J. Kodaira , H. Sakamoto , Y. Mizuguchi , T. Hayashi , K.L. Tan

引用次数: 2

Cryopumping for fusion reactors 用于核聚变反应堆的低温泵浦

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90002-4

Douglas W. Sedgley, Albert G. Tobin, Thomas H. Batzer, Wayne R. Call

{"title":"Cryopumping for fusion reactors","authors":"Douglas W. Sedgley, Albert G. Tobin, Thomas H. Batzer, Wayne R. Call","doi":"10.1016/0167-899X(87)90002-4","DOIUrl":"10.1016/0167-899X(87)90002-4","url":null,"abstract":"<div><p>Fusion reactors will exhaust large volumes of hydrogen species and helium, and cryopumps can satisfy the pumping needs. Two programs described here were undertaken to develop the high performance, continuous operation required. The capability of charcoal as a cryogenic sorbent was optimized and improved by use of specific charcoal types and grades, and by use of thermally conductive bonds for attaching the charcoal to the cryogenically cooled substrate. A 30% demonstrated pumping speed improvement is significant for a system in which the pump dimensions are measured in tens of square meters.</p><p>An automatically controlled continuous duty cryopump system was developed, fabricated and demonstrated. The system pumps deuterium, and can be readily modified to pump helium by addition of a sorbent such as charcoal. This two-unit system has one unit being regenerated while the other unit is pumping. It is prototypical of a fusion reactor pump in which five units would be pumping for each unit that is being regenerated. Low tritium holdup is projected for an operational installation.</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 2","pages":"Pages 149-163"},"PeriodicalIF":0.0,"publicationDate":"1987-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(87)90002-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72806422","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: 13

Contents of part I 第一部分内容

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90012-7

引用次数: 0

Dynamic analysis of the TFTR bumper limiter TFTR缓冲器限位器的动力学分析

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90001-2

Irving J. Zatz

{"title":"Dynamic analysis of the TFTR bumper limiter","authors":"Irving J. Zatz","doi":"10.1016/0167-899X(87)90001-2","DOIUrl":"10.1016/0167-899X(87)90001-2","url":null,"abstract":"<div><p>Of the many components and systems comprising a fusion reactor like the Tokamak Fusion Test Reactor (TFTR), few, if any, are subjected to more extreme and severe conditions than the protective armor for the interior vacuum vessel wall. The primary TFTR limiter, referred to as the Phase II bumper limiter, provides protection of the inner vacuum vessel wall from neutral beam shine through, normal plamsa loads, and major disruptive instabilities. The highly transient nature of forces and temperatures induced by these conditions produces significant dynamic responses in various parts of the bumper limiter structural system. This paper addresses the incorporation of a finite element dynamic analysis in the study of bumper limiter behavior when subjected to several electromagnetic load scenarios. These loads, due to a variety of realistic plasma conditions, were used in the interactive design and optimization of limiter components and support locations and flexibilities which enable the structure to perform within established criteria.</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 2","pages":"Pages 141-148"},"PeriodicalIF":0.0,"publicationDate":"1987-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(87)90001-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87367454","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

Optimal laser heating of plasmas confined in strong solenoidal magnetic fields 强螺线管磁场中等离子体的最佳激光加热

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90003-6

E. Javier Vitela, A. Ziya Akcasu

引用次数: 1

3. Advanced design of the R-Tokamak 3.r -托卡马克的先进设计

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90015-2

K. Matsuoka, K. Yamazaki, S. Kitagawa, Y. Ogawa

{"title":"3. Advanced design of the R-Tokamak","authors":"K. Matsuoka, K. Yamazaki, S. Kitagawa, Y. Ogawa","doi":"10.1016/0167-899X(87)90015-2","DOIUrl":"10.1016/0167-899X(87)90015-2","url":null,"abstract":"<div><p>A medium-sized DT burning tokamak has been designed with low-activation Al-alloys. We can obtain a large plasma current up to 4.5 MA with an elongation of 2.3, by taking advantage of the good shell effect of Al-alloy vessel and by applying the appropriate feedback control system. Such a large current is effective for the improvement of confinement and high β-value.</p><p>To obtain these plasma parameters, PF coils are placed inside TFC. Single pancake windings and their connection by welding remove complexity originated from this configuration. By the use of keys in the extended wedge region and large shear panels the displacement of TFC caused by large overturning moment is suppressed to be less than 1 mm.</p><p>For reduction of induced activity, almost all the components have been designed with Al-alloys except TFC and inboard PFC conductors. The newly developed Al-alloy has been applied to the vacuum vessel, where the new structure of one-turn break is adopted using Al<sub>2</sub>O<sub>3</sub> ceramic spraying. Gamma-rays from activated copper conductor in TFC and inboard PFC are shielded by a lead plate located between the vacuum vessel and PFC. This concept would be extended to devices which aim at <em>Q</em> ⪢ 1 and much longer burning time, if all the coils are made of Al-alloy of which contents of impurity and alloying element are well-controlled.</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 3","pages":"Pages 335-355"},"PeriodicalIF":0.0,"publicationDate":"1987-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(87)90015-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81536543","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

4. Alpha-particle diagnostics in the reacting plasma experiment 4. 反应等离子体实验中的α粒子诊断

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90022-X

K.N. Sato

引用次数: 1

Organic coolants and their applications to fusion reactors 有机冷却剂及其在聚变反应堆中的应用

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90006-1

P. Gierszewski, R.E. Hollies

{"title":"Organic coolants and their applications to fusion reactors","authors":"P. Gierszewski, R.E. Hollies","doi":"10.1016/0167-899X(87)90006-1","DOIUrl":"10.1016/0167-899X(87)90006-1","url":null,"abstract":"<div><p>Organic coolants offer a unique set of characteristics for fusion applications. Their main advantages include high temperature (670 K) but low pressure (2 MPa) operation, limited reactivity with lithium and lithium—lead, reduced corrosion and activation, good heat transfer capabilities, no MHD effects, and an operating temperature range that extends to room temperature. The major disadvantages are decomposition and flammability.</p><p>The organic fluid characteristics are described in sufficient detail to allow fusion system designers to evaluate organic coolants for specific applications. Analyses are presented for organic-cooled blankets, first walls, high heat flux components and thermal power cycles. Designs are identified that take advantage of organic coolant features, yet have fluid decomposition related costs that are a small fraction of the overall cost of electricity. Particularly interesting applications include organic-cooled high heat flux components (up to about 8 MW/m<sup>2</sup>) for use with liquid metal cooled blankets.</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 2","pages":"Pages 223-236"},"PeriodicalIF":0.0,"publicationDate":"1987-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(87)90006-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83816464","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: 7

3. Development of a high power ion source and a neutral beam injector on a 10 MW test stand 3.大功率离子源和中性束注入器在10mw试验台上的研制

Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy Pub Date : 1987-01-01 DOI: 10.1016/0167-899X(87)90021-8

Y. Oka, O. Kaneko, K. Sakurai, T. Kuroda

引用次数: 9