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Journal of Nuclear Energy. Part B. Reactor Technology最新文献

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A Liquid Loop as a Radiation Source, with Particular Reference to Radiation Chemistry 作为辐射源的液体回路，特别涉及辐射化学
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30009-2
Iu.S. Riabukhin, A.Kh. Breger
{"title":"A Liquid Loop as a Radiation Source, with Particular Reference to Radiation Chemistry","authors":"Iu.S. Riabukhin,&nbsp;A.Kh. Breger","doi":"10.1016/S0368-3273(15)30009-2","DOIUrl":"10.1016/S0368-3273(15)30009-2","url":null,"abstract":"<div><p>A discussion is given of the various applications of powerful radiation fluxes from reactors, particularly in radiation chemistry. An arrangement is described in which a liquid loop is used in conjunction with a hole which brings out the γ-flux into an external apparatus; the activated material forms only one radio-isotope, which decays to stable products. Working formulae and graphs are deduced from which the γ-fluxes can be calculated and from which can be derived the loop parameters which provide the best conditions.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 2","pages":"Pages 109-115"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30009-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74333433","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 Reactor Control and Instrumentation, J.H. Bowen, E.F.O. Masters. Temple Press (1959), (Nucl. Engng. Monograph), 78 pp., 12s 6d 核反应堆控制与仪器，J.H. Bowen, E.F.O. Masters。神庙出版社(1959)，(英文版)。Engng。专著)，78页，12s - 6d
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30008-0
A. Hussey
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引用次数: 0
Mass-Transport and Corrosion of Iron-Based Alloys in Liquid Metals 铁基合金在液态金属中的传质与腐蚀
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30003-1
G.W. Horsley
{"title":"Mass-Transport and Corrosion of Iron-Based Alloys in Liquid Metals","authors":"G.W. Horsley","doi":"10.1016/S0368-3273(15)30003-1","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30003-1","url":null,"abstract":"<div><p>The application of mass-transport equations to the corrosion of metals by liquid metals is discussed. Calculated corrosion rates are compared with experimentally determined rates. It is concluded that diffusion controlled solution attack, although significant, may not under conditions of interest to reactor engineers be as serious as either inter-granular attack or chemically assisted mass-transport. The mechanism of inter-granular attack, the thermodynamics of an example of chemically assisted mass-transport, the role of oxygen in sodium-stainless steel circuits and methods of reducing mass-transport of iron are discussed.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 2","pages":"Pages 84-91"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30003-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90031791","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
Abstracts and Titles of Future Papers 未来论文的摘要和标题
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30015-8
{"title":"Abstracts and Titles of Future Papers","authors":"","doi":"10.1016/S0368-3273(15)30015-8","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30015-8","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 2","pages":"Pages 141-144"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30015-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"137257806","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
Sources of Gamma Radiation in a Reactor Core 反应堆堆芯的伽马辐射源
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30005-5
Matts Roos
{"title":"Sources of Gamma Radiation in a Reactor Core","authors":"Matts Roos","doi":"10.1016/S0368-3273(15)30005-5","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30005-5","url":null,"abstract":"<div><p>In a thermal reactor the gamma ray sources of importance for shielding calculations and related aspects are (1) fission, (2) decay of fission products, (3) capture processes in fuel, poison and other materials, (4) inelastic scattering in the fuel and (5) decay of capture products. The energy release and the gamma ray spectra of these sources have been compiled or estimated from the latest information available, and the results are presented in a general way to permit application to any thermal reactor, fuelled with a mixture of <sup>235</sup>U and <sup>238</sup>U. As an example the total spectrum and the spectrum of radiation escaping from a fuel rod in the Swedish R3-reactor are presented.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 2","pages":"Pages 98-104"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30005-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91719528","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: 5
An Empirical Correlation of the Experimental Data on Homogeneous, Highly Enriched, Uranium and Uranium-Hydrogen Critical Assemblies—II. Changes in Physical Properties 均质、高富集、铀和铀氢临界组件实验数据的经验关联——ⅱ。物理性质的变化
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30004-3
B.G. Owen, R.A. Gibson
{"title":"An Empirical Correlation of the Experimental Data on Homogeneous, Highly Enriched, Uranium and Uranium-Hydrogen Critical Assemblies—II. Changes in Physical Properties","authors":"B.G. Owen,&nbsp;R.A. Gibson","doi":"10.1016/S0368-3273(15)30004-3","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30004-3","url":null,"abstract":"<div><p>An empirical correlation is presented which enables a constant <em>B</em><sub>0</sub> to be determined in terms of the mass concentration of <sup>235</sup>U, the atomic ratio H/<sup>235</sup>U and the excess multiplication (<em>k</em><sub>∞</sub> – 1). This constant <em>B</em><sub>0</sub> behaves similarly to the material buckling and from it can be determined the physical size of a hydrogeneous uranium critical assembly.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 2","pages":"Pages 92-97"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30004-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91737552","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
The Use of Electronic Digital Computers in a Study of High Temperature Gas Cooled Reactors 电子数字计算机在高温气冷堆研究中的应用
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30063-8
D.V. Wordsworth
{"title":"The Use of Electronic Digital Computers in a Study of High Temperature Gas Cooled Reactors","authors":"D.V. Wordsworth","doi":"10.1016/S0368-3273(15)30063-8","DOIUrl":"10.1016/S0368-3273(15)30063-8","url":null,"abstract":"<div><p>The following paper is in the form of a review of the scope of high speed computer methods as applied to a particular reactor design study in connexion with which the author has been responsible for the mathematical work. For a more general review the reader is referred to, e.g., H<span>owlett</span> (1958). By reviewing a particular design study the author has been able to discuss certain aspects of the work in some degree of detail, but even so it has not been possible in the space available to do more than review the <em>types</em> of problems to which machine methods have been applied in the pursuance of this specific study: the derivation of equations (most of which are, however, now well-known) and the evaluation of results has had to be omitted. It is hoped to publish more detailed papers dealing with more specialized branches of the subject in subsequent issues of Reactor Technology.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 1","pages":"Pages 25-34"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30063-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85298463","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
A measurement of the gamma-ray intensity produced by extended source 对扩展源产生的伽马射线强度的测量
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30068-7
E.E. Kovalev, V.I. Popov, L.N. Smirenny, Yu.S. Khokhlov
{"title":"A measurement of the gamma-ray intensity produced by extended source","authors":"E.E. Kovalev,&nbsp;V.I. Popov,&nbsp;L.N. Smirenny,&nbsp;Yu.S. Khokhlov","doi":"10.1016/S0368-3273(15)30068-7","DOIUrl":"10.1016/S0368-3273(15)30068-7","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 1","pages":"Pages 51-52"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30068-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82223105","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
The absorption of 198Au 60Co and 24Na γ-rays in water 水中对198Au、60Co和24Na γ射线的吸收
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30072-9
V.N. Sakharov
{"title":"The absorption of 198Au 60Co and 24Na γ-rays in water","authors":"V.N. Sakharov","doi":"10.1016/S0368-3273(15)30072-9","DOIUrl":"10.1016/S0368-3273(15)30072-9","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 1","pages":"Pages 55-57"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30072-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76582931","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
On the measurement of resonance neutron adsorption in heterogeneous U-D2O systems 非均相U-D2O体系中共振中子吸附量的测定
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1959-01-01 DOI: 10.1016/S0368-3273(15)30073-0
B.F. Belkin, P.A. Krupchitsky, Yu.V. Orlov
{"title":"On the measurement of resonance neutron adsorption in heterogeneous U-D2O systems","authors":"B.F. Belkin,&nbsp;P.A. Krupchitsky,&nbsp;Yu.V. Orlov","doi":"10.1016/S0368-3273(15)30073-0","DOIUrl":"10.1016/S0368-3273(15)30073-0","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 1","pages":"Pages 57-60"},"PeriodicalIF":0.0,"publicationDate":"1959-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30073-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79889392","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
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