Annals of Nuclear Science and Engineering最新文献

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International meeting on reactor heat transfer at Karlsruhe: (A critical review) 卡尔斯鲁厄反应堆传热国际会议:(评论)
Annals of Nuclear Science and Engineering Pub Date : 1974-02-01 DOI: 10.1016/0302-2927(74)90060-9
F. Berger
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引用次数: 0
Kinetics and noise analysis of zero-power reactors: An NPY-project report 零功率反应堆的动力学和噪声分析:一份npy项目报告
Annals of Nuclear Science and Engineering Pub Date : 1974-02-01 DOI: 10.1016/0302-2927(74)90062-2
A.Edward Profio
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引用次数: 0
The dynamical behaviour of cylindrical structures in axial flow 轴向流动中圆柱结构的动力特性
Annals of Nuclear Science and Engineering Pub Date : 1974-02-01 DOI: 10.1016/0302-2927(74)90055-5
M.P. Païdoussis
{"title":"The dynamical behaviour of cylindrical structures in axial flow","authors":"M.P. Païdoussis","doi":"10.1016/0302-2927(74)90055-5","DOIUrl":"10.1016/0302-2927(74)90055-5","url":null,"abstract":"<div><p>This is a review on the effect of axial flow on cylindrical structures. It is shown that axial flow may cause <em>fluidelastic instabilities</em> at sufficiently high flow velocities. However, for the range of flow velocities and other parameters pertaining to most industrial systems, the effect of purely axial, uniform steady flow is to damp free motions. Nevertheless, departures from such ideal flow conditions induce small amplitude vibration, termed <em>sub-critical</em> vibration. The underlying mechanism of this vibration is examined and the various means available for predicting its amplitude are discussed. These latter are either empirical or analytical (generally semi-empirical); the analytical methods are further classified into three categories accordingly as they postulate the vibration to be <em>forced, parametric</em> or <em>self-excited</em>. The measure of success achieved in predicting sub-critical vibration amplitude is discussed, and possible reasons for its being generally poor. At present, the amplitude may be predicted typically to within one order of magnitude.</p></div>","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 2","pages":"Pages 83-106"},"PeriodicalIF":0.0,"publicationDate":"1974-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0302-2927(74)90055-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85798179","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: 32
Plasma engineering 等离子体工程
Annals of Nuclear Science and Engineering Pub Date : 1974-02-01 DOI: 10.1016/0302-2927(74)90061-0
G.R. Hopkins
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引用次数: 0
Experience and trends in nuclear law 核法的经验和趋势
Annals of Nuclear Science and Engineering Pub Date : 1974-02-01 DOI: 10.1016/0302-2927(74)90063-4
James P. Hogan
{"title":"Experience and trends in nuclear law","authors":"James P. Hogan","doi":"10.1016/0302-2927(74)90063-4","DOIUrl":"10.1016/0302-2927(74)90063-4","url":null,"abstract":"","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 2","pages":"Page 164"},"PeriodicalIF":0.0,"publicationDate":"1974-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0302-2927(74)90063-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"92944325","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
International meeting on reactor heat transfer at Karlsruhe 卡尔斯鲁厄反应堆传热国际会议
Annals of Nuclear Science and Engineering Pub Date : 1974-02-01 DOI: 10.1016/0302-2927(74)90060-9
F.P. Berger
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引用次数: 0
A review of the symposium on the Principles and Standards of Reactor Safety—1973 1973年反应堆安全原则与标准研讨会综述
Annals of Nuclear Science and Engineering Pub Date : 1974-01-01 DOI: 10.1016/0302-2927(74)90094-4
J. Shaw
{"title":"A review of the symposium on the Principles and Standards of Reactor Safety—1973","authors":"J. Shaw","doi":"10.1016/0302-2927(74)90094-4","DOIUrl":"10.1016/0302-2927(74)90094-4","url":null,"abstract":"<div><p>A symposium on the Principles and Standards of Reactor Safety organised by the International Atomic Energy Agency (IAEA) was held at the Nuclear Research Centre, Julich, Federal Republic of Germany from 5th to 9th February, 1973.</p><p>The conference was attended by some 275 delegates from 32 countries; the majority coming from Belgium, France, Germany, Italy, Sweden, U.S.A. and the United Kingdom. The papers presented at the conference were divided into nine sessions under the following general headings. </p><ul><li><span>1.</span><span><p>(a) Philosophy of safety design.</p></span></li><li><span>2.</span><span><p>(b) Quality assurance and reliability.</p></span></li><li><span>3.</span><span><p>(c) Methods of safety evaluation for power reactors.</p></span></li><li><span>4.</span><span><p>(d) Design for natural and man-made disasters.</p></span></li><li><span>5.</span><span><p>(e) Siting considerations for power reactors.</p></span></li><li><span>6.</span><span><p>(f) Standards and criteria for the design and construction of power reactors.</p></span></li><li><span>7.</span><span><p>(g) Design safety features.</p></span></li><li><span>8.</span><span><p>(h) Safety in high temperature gas cooled reactors.</p></span></li><li><span>9.</span><span><p>(i) Safety in operation.</p></span></li></ul><p>It is intended in this report to summarise the highlights of the symposium from a personal viewpoint.</p></div>","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 1","pages":"Pages 55-65"},"PeriodicalIF":0.0,"publicationDate":"1974-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0302-2927(74)90094-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85445665","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
Nuclear power reactor instrumentation systems handbook 核电反应堆仪表系统手册
Annals of Nuclear Science and Engineering Pub Date : 1974-01-01 DOI: 10.1016/0302-2927(74)90100-7
H.A. Thomas
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引用次数: 2
Vol. 2: Topics in current aerosol research (part 1) 第2卷:当前气溶胶研究的主题(第一部分)
Annals of Nuclear Science and Engineering Pub Date : 1974-01-01 DOI: 10.1016/0302-2927(74)90098-1
M.M.R. Williams
{"title":"Vol. 2: Topics in current aerosol research (part 1)","authors":"M.M.R. Williams","doi":"10.1016/0302-2927(74)90098-1","DOIUrl":"10.1016/0302-2927(74)90098-1","url":null,"abstract":"","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 1","pages":"Page 71"},"PeriodicalIF":0.0,"publicationDate":"1974-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0302-2927(74)90098-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"106311907","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
Application of gas-cooled reactor technology to the fast breeder concept 气冷堆技术在快中子增殖概念中的应用
Annals of Nuclear Science and Engineering Pub Date : 1974-01-01 DOI: 10.1016/0302-2927(74)90091-9
Peter Fortescue
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引用次数: 0
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