{"title":"International meeting on reactor heat transfer at Karlsruhe: (A critical review)","authors":"F. Berger","doi":"10.1016/0302-2927(74)90060-9","DOIUrl":"https://doi.org/10.1016/0302-2927(74)90060-9","url":null,"abstract":"","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"40 1","pages":"157-161"},"PeriodicalIF":0.0,"publicationDate":"1974-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73044847","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}
{"title":"Kinetics and noise analysis of zero-power reactors: An NPY-project report","authors":"A.Edward Profio","doi":"10.1016/0302-2927(74)90062-2","DOIUrl":"https://doi.org/10.1016/0302-2927(74)90062-2","url":null,"abstract":"","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 2","pages":"Pages 163-164"},"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)90062-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91650663","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}
{"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}
{"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}
{"title":"International meeting on reactor heat transfer at Karlsruhe","authors":"F.P. Berger","doi":"10.1016/0302-2927(74)90060-9","DOIUrl":"https://doi.org/10.1016/0302-2927(74)90060-9","url":null,"abstract":"<div><p>The meeting gave a good picture of the main problems being presently pursued in convective reactor heat transfer. Models for the prediction of the flow structures and temperature distributions in fuel subassemblies have made significant progress and are reaching a high level of sophistication. These models cover steady one-phase and two-phase flow as well as transient and accident conditions. Experiments on rod clusters investigating mixing in the cluster and the effect of spacers on it, as well as voidage and velocity distributions in subchannels are providing improved input data. Heat transfer on rough surfaces is still being studied, but no general reliable method for predicting the effect of such surfaces seems to be available yet. New data have been obtained on heat transfer in less common gases. Research on burnout seems to be concentrated mainly on transient situations. Increased activity is noticeable in the research of flow and heat transfer in typical heat exchangers of nuclear plant. In the field of reactor safety the main effort is concentrated on studies of the effect of blockages and accident conditions in fast reactor fuel assemblies and of blow-down and emergency flooding in water reactors. It is probably in this region that further experimentation is most urgently required. Some important problems not covered at the meeting have been pointed out on the previous pages.</p></div>","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 2","pages":"Pages 157-161"},"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)90060-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91650662","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}
{"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}
{"title":"Nuclear power reactor instrumentation systems handbook","authors":"H.A. Thomas","doi":"10.1016/0302-2927(74)90100-7","DOIUrl":"10.1016/0302-2927(74)90100-7","url":null,"abstract":"","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 1","pages":"Pages 71-72"},"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)90100-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84169232","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}
{"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}
{"title":"Application of gas-cooled reactor technology to the fast breeder concept","authors":"Peter Fortescue","doi":"10.1016/0302-2927(74)90091-9","DOIUrl":"https://doi.org/10.1016/0302-2927(74)90091-9","url":null,"abstract":"","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 1","pages":"Pages 21-29"},"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)90091-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"137226401","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}