Nuclear Structural Engineering最新文献

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Experimental studies on impact strength of weld metal of arc welding electrode for reactor pressure vessel 反应堆压力容器用弧焊焊条焊缝金属冲击强度试验研究
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90011-6
Shinji Kimura
{"title":"Experimental studies on impact strength of weld metal of arc welding electrode for reactor pressure vessel","authors":"Shinji Kimura","doi":"10.1016/0369-5816(65)90011-6","DOIUrl":"10.1016/0369-5816(65)90011-6","url":null,"abstract":"<div><p>The experimental studies were carried out on the influences of Mn and Si contents upon the impact strength of MnSi lime basis type weld metal in order to manufacture the arc welding electrode for the welding of the reactor pressure vessel of the Advanced Calder Hall type. The test results showed that it was possible to obtain the MnSi lime basis type weld metal with high impact strength by increasing the Mn content of weld metal in welding of heavy thick plate.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 251-254"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90011-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84183546","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 status report on prestressed-concrete reactor pressure vessel technology 预应力混凝土反应堆压力容器技术现状报告
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90007-4
M. Bender
{"title":"A status report on prestressed-concrete reactor pressure vessel technology","authors":"M. Bender","doi":"10.1016/0369-5816(65)90007-4","DOIUrl":"10.1016/0369-5816(65)90007-4","url":null,"abstract":"<div><p>The evolution of concrete pressure vessel design is traced in this report, and a summary of the current applications of prestressed concrete for reactor pressure vessels is presented. Important design considerations and methods for design evaluation are discussed. It is concluded that a basis for design compatible with the ACI and ASME pressure vessel codes is evolving, but the maximum pressure limits for which prestressed concrete can be used are yet to be established.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 206-223"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90007-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75324816","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
A note on plastic expansion of irradiated spherical shells 辐照球壳的塑性膨胀注释
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90003-7
Antoni Sawczuk
{"title":"A note on plastic expansion of irradiated spherical shells","authors":"Antoni Sawczuk","doi":"10.1016/0369-5816(65)90003-7","DOIUrl":"10.1016/0369-5816(65)90003-7","url":null,"abstract":"<div><p>Finite plastic expansion of a thick-walled spherical vessel is studied in presence of neutron radiation. Due to irradiation the yield stress and the hardening modulus vary across the shell wall. The pressure-expansion relation is obtained in case of combined linear hardening and linear attenuation.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 155-158"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90003-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83028650","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
Strength problems of reactor steel pressure vessel of large dimensions 大尺寸反应堆钢压力容器的强度问题
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90006-2
Jaroslav Němec
{"title":"Strength problems of reactor steel pressure vessel of large dimensions","authors":"Jaroslav Němec","doi":"10.1016/0369-5816(65)90006-2","DOIUrl":"10.1016/0369-5816(65)90006-2","url":null,"abstract":"<div><p>The production of an operationally reliable pressure vessel for the reactor is one of the difficult tasks encountered in many projects of large nuclear power stations. These steel vessels have large dimensions (diameters from 3 m to 8 m) and a comparatively high internal pressure so that the basic wall thickness is sometimes amounting to several tens of centimetres. According to the type of nuclear reactor it is possible to divide the pressure vessels in the bodies working at high temperature (&gt;250°C) and low temperature (&lt;250°C). This paper concerns the second group of vessels, where it is not necessary to consider the creep of metals. In particular, the effect of size on quasi-brittle strength of pressure vessel steel and the effect of pulsating loads on the strength of vessels are discussed. It is emphasized, that the selection of materials, shape and size of large welded reactor pressure vessels only on the basic of standard tests of mechanical properties of materials performed with small test specimens is completely inadequate. Special attention is called to the great importance of the size factor.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 197-205"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90006-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72704564","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
Vorschlag für ein systematisches bewertungsverfahren zur wahl von reaktorstandorten 关于查明反应堆选举的系统评估程序的建议
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90010-4
H. Luks
{"title":"Vorschlag für ein systematisches bewertungsverfahren zur wahl von reaktorstandorten","authors":"H. Luks","doi":"10.1016/0369-5816(65)90010-4","DOIUrl":"10.1016/0369-5816(65)90010-4","url":null,"abstract":"<div><p>The choice of reactor sites is determined by more numerous and diverse considerations than are involved in the site selection for a conventional industrial plant. The question of site selection for nuclear reactors and nuclear research centers is still a matter of much controversy. The present paper attempts to develop a systematic procedure for guidance in site selection considering hydrologic, geologic, topographic, and meteorologic conditions, as well as parameters of population density distribution, interests of neighbouring industries, agricultural use of the environments, and traffic situation. The task is to select in a systematic way, from a number of possible suitable sites the one representing an overall optimum. As illustrative examples some reactor sites in Germany are analysed using the suggested procedure. The intended use of the procedure is, of course, not aimed to the comparison of sites for different reactors, but to the comparison of different sites for a specific reactor facility.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 239-250"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90010-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85104013","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
Conceptual design of a prestressed concrete reactor pressure vessel 预应力混凝土反应堆压力容器概念设计
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90008-6
Chen Pang Tan
{"title":"Conceptual design of a prestressed concrete reactor pressure vessel","authors":"Chen Pang Tan","doi":"10.1016/0369-5816(65)90008-6","DOIUrl":"10.1016/0369-5816(65)90008-6","url":null,"abstract":"<div><p>A conceptual design of a horizontal cylindrical prestressed concrete reactor pressure vessel for housing a large gas-cooled high power-density reactor and power generating equipment is presented. The evolution of the geometry of the vessel design is described. Structural considerations for a full chamber-size opening are outlined. The choice of tendons and anchorages is discussed. Consideration is given to the practical aspects of construction.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 224-231"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90008-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74403246","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
Radiation and creep analysis of strains and stresses in annular fuel elements 环形燃料元件应变和应力的辐射和蠕变分析
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90002-5
Benjamin M. Ma, Glenn Murphy
{"title":"Radiation and creep analysis of strains and stresses in annular fuel elements","authors":"Benjamin M. Ma,&nbsp;Glenn Murphy","doi":"10.1016/0369-5816(65)90002-5","DOIUrl":"10.1016/0369-5816(65)90002-5","url":null,"abstract":"<div><p>A theoretical analysis for the determination of strains and stresses produced in long, annular reactor fuel elements is presented. In the analysis, primary effects of thermal-cycling growth, irradiation growth, swelling, creep and neutron flux levels developed in the fuel material are taken into account.</p><p>An exact solution based on a product of the modified Bessel functions and the Fourier cosine function, and a simplified, approximate solution of the parabolic function for thermal neutron flux distribution are obtained from the simple diffusion equations. After the rate of volumetric heat generation has been determined, the radial temperature distribution in the fuel is found by using Poisson's equation of heat conduction.</p><p>From some basic assumptions the fundamental equations of displacement-strain relations, compatibility, incompressibility, equilibrium, and yield criterion are established. The strain and stress equations for the fuel elements are derived. From the calculated results of an illustrative example, the neutron flux levels, degree of thermal and radiation dilatation, thickness and properties of the cladding material are found to have important effects on the strain and stress distributions produced in the fuel elements.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 141-154"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90002-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77850726","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
Raumgewichtsbestimmung mit radioaktiven isotopen 大气层的放射性同位素
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90013-X
Arnošt Hönig
{"title":"Raumgewichtsbestimmung mit radioaktiven isotopen","authors":"Arnošt Hönig","doi":"10.1016/0369-5816(65)90013-X","DOIUrl":"10.1016/0369-5816(65)90013-X","url":null,"abstract":"","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 256-257"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90013-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"92876000","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
Analysis of axisymmetric redundant structures 轴对称冗余结构分析
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90004-9
Z. Zudans
{"title":"Analysis of axisymmetric redundant structures","authors":"Z. Zudans","doi":"10.1016/0369-5816(65)90004-9","DOIUrl":"10.1016/0369-5816(65)90004-9","url":null,"abstract":"<div><p>Based on the principle of complementary energy, a system of compatibility equations for axisymmetric structures is derived. Using the compatibility equations, an analysis method, suitable for use with the digital computer and for hand computations is developed. Equations for analysis of most of the usually encountered types of free bodies are given. Method for evaluation of matrix contributions is described, and a complete numerical sample is reproduced at the end of this article. Analysis as described herein has been programmed at The Franklin Institute and successfully used by the author for numerous reactor vessel, heat exchanger and other axisymmetric structure analyses.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 159-185"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90004-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78336722","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
Kernenergieantriebe für handelsschiffe 核能
Nuclear Structural Engineering Pub Date : 1965-02-01 DOI: 10.1016/0369-5816(65)90014-1
K.R. Repetzki
{"title":"Kernenergieantriebe für handelsschiffe","authors":"K.R. Repetzki","doi":"10.1016/0369-5816(65)90014-1","DOIUrl":"https://doi.org/10.1016/0369-5816(65)90014-1","url":null,"abstract":"","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 2","pages":"Pages 257-258"},"PeriodicalIF":0.0,"publicationDate":"1965-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90014-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"92050580","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
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