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Temperature distribution in gamma-active spheres 伽马活跃球的温度分布
Nuclear Structural Engineering Pub Date : 1965-07-01 DOI: 10.1016/0369-5816(65)90145-6
V.K. Sundaram, D.V. Gopinath, A.K. Ganguly
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引用次数: 2
Limit analysis of axisymmetric intersecting shells of revolution 轴对称交转壳的极限分析
Nuclear Structural Engineering Pub Date : 1965-07-01 DOI: 10.1016/0369-5816(65)90138-9
F. Ellyin, A.N. Sherbourne
{"title":"Limit analysis of axisymmetric intersecting shells of revolution","authors":"F. Ellyin,&nbsp;A.N. Sherbourne","doi":"10.1016/0369-5816(65)90138-9","DOIUrl":"10.1016/0369-5816(65)90138-9","url":null,"abstract":"<div><p>The general theory of the plastic analysis of axisymmetric shells of revolution is discussed and conditions for the construction of a complete solution and bounds to it are defined. It is shown that the various approaches to the collapse of the cylinder/sphere intersection may be placed in one of two categories. Approximate solutions, in conjunction with yield surfaces for cylindrical shells, are outlined.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"2 1","pages":"Pages 86-91"},"PeriodicalIF":0.0,"publicationDate":"1965-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90138-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73022924","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: 9
An electric analog computer for nuclear fuel shipping cask fire tests 一种用于核燃料运输桶着火试验的电子模拟计算机
Nuclear Structural Engineering Pub Date : 1965-07-01 DOI: 10.1016/0369-5816(65)90135-3
C.F. Bonilla, A.L. Strupczewski
{"title":"An electric analog computer for nuclear fuel shipping cask fire tests","authors":"C.F. Bonilla,&nbsp;A.L. Strupczewski","doi":"10.1016/0369-5816(65)90135-3","DOIUrl":"10.1016/0369-5816(65)90135-3","url":null,"abstract":"<div><p>Description of an electrical analog network for the thermal analysis of nuclear fuel shipping casks under fire accident conditions. The network allows to simulate the thermal behaviour of a wide range of cask dimensions for any given fire temperature curve. Changes in thermal properties of the materials involved, melting of the lead shield, and any changes in the heat transfer coefficients during the fire may all be presented.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"2 1","pages":"Pages 40-47"},"PeriodicalIF":0.0,"publicationDate":"1965-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90135-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72583293","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 elastic-plastic analysis of stresses and strains at hyperbolic notches in flat plates 平板双曲缺口处应力和应变的弹塑性分析
Nuclear Structural Engineering Pub Date : 1965-07-01 DOI: 10.1016/0369-5816(65)90139-0
I.S. Tuba
{"title":"An elastic-plastic analysis of stresses and strains at hyperbolic notches in flat plates","authors":"I.S. Tuba","doi":"10.1016/0369-5816(65)90139-0","DOIUrl":"10.1016/0369-5816(65)90139-0","url":null,"abstract":"<div><p>An elastic-plastic solution is given for pure tension, pure bending and pure shear at hyperbolic notches in flat plates. In order to illustrate the practicality of the formulation and method of solution three problems are illustrated, representing the three different types of loading conditions.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"2 1","pages":"Pages 92-101"},"PeriodicalIF":0.0,"publicationDate":"1965-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90139-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74609009","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: 3
Thermal stress analysis of conical shells 锥形壳的热应力分析
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90147-X
F.J. Witt
{"title":"Thermal stress analysis of conical shells","authors":"F.J. Witt","doi":"10.1016/0369-5816(65)90147-X","DOIUrl":"10.1016/0369-5816(65)90147-X","url":null,"abstract":"<div><p>The differential equation of a conical shell subjected to axisymmetrical temperature distributions is derived. The temperature distributions may vary in the meridional direction and linearly through the thickness. In order to obtain a particular solution to the differential equation, the expression for the temperature distributions is assumed to be the sum of hyperbolic and cubic functions. The particular solution is superposed on the homogeneous solution and all the formulae for a complete analysis are given.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 5","pages":"Pages 449-456"},"PeriodicalIF":0.0,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90147-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74166402","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: 6
Radiation effects on metals and neutron dosimetry: Proceedings of a Symposium, 4th Pacific Area Meeting ASTM, Los Angeles, Calif., October 2–3, 1962. ASTM-STP-341, ASTM, Philadelphia, Pennsylvania (1963). 409 pages, $ 15.00. 辐射对金属和中子剂量学的影响:第四届太平洋地区ASTM会议论文集，洛杉矶，加州，1962年10月2-3日。ASTM- stp -341, ASTM，费城，宾夕法尼亚州(1963)。409页，15美元。
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90152-3
A. Rossin
{"title":"Radiation effects on metals and neutron dosimetry: Proceedings of a Symposium, 4th Pacific Area Meeting ASTM, Los Angeles, Calif., October 2–3, 1962. ASTM-STP-341, ASTM, Philadelphia, Pennsylvania (1963). 409 pages, $ 15.00.","authors":"A. Rossin","doi":"10.1016/0369-5816(65)90152-3","DOIUrl":"https://doi.org/10.1016/0369-5816(65)90152-3","url":null,"abstract":"","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"19 1","pages":"500-501"},"PeriodicalIF":0.0,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74141905","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
An analytical solution of multi-group removal-diffusion equations, in plane multi-layered, reactor shield system 平面多层反应堆屏蔽系统中多群移除扩散方程的解析解
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90150-X
L.W. Szymendera
{"title":"An analytical solution of multi-group removal-diffusion equations, in plane multi-layered, reactor shield system","authors":"L.W. Szymendera","doi":"10.1016/0369-5816(65)90150-X","DOIUrl":"10.1016/0369-5816(65)90150-X","url":null,"abstract":"<div><p>This paper gives the analytical solution of the set of differential equations describing, in the multigroup removal-diffusion approximation of Boltzmann's transport equation, the neutron flux distributions in the multi-layered plane shield of a nuclear reactor. The solution is obtained in closed form of a linear combination of some well-defined auxiliary expression, which can be easily integrated and differentiated.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 5","pages":"Pages 476-489"},"PeriodicalIF":0.0,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90150-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84756274","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
Problems in the design and construction of large reactor vessels 大型反应堆容器设计与建造中的问题
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90148-1
A.L. Gaines, L. Porse
{"title":"Problems in the design and construction of large reactor vessels","authors":"A.L. Gaines,&nbsp;L. Porse","doi":"10.1016/0369-5816(65)90148-1","DOIUrl":"10.1016/0369-5816(65)90148-1","url":null,"abstract":"<div><p>The new “ASME boiler and pressure vessel code for nuclear vessels” permits design of nuclear reactor vessels for water reactor plants of up to 1500 MW. The problems of design, material procurement, and inspection are surveyed.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 5","pages":"Pages 457-465"},"PeriodicalIF":0.0,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90148-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75757291","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
Radiation effects on metals and neutron dosimetry 辐射对金属的影响和中子剂量学
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90152-3
A.D. Rossin
{"title":"Radiation effects on metals and neutron dosimetry","authors":"A.D. Rossin","doi":"10.1016/0369-5816(65)90152-3","DOIUrl":"https://doi.org/10.1016/0369-5816(65)90152-3","url":null,"abstract":"","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 5","pages":"Pages 500-501"},"PeriodicalIF":0.0,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90152-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"92095558","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
Transient temperature distributions in cylindrical fuel-element end caps 圆柱形燃料元件端盖内的瞬态温度分布
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90146-8
Benjamin M. Ma
{"title":"Transient temperature distributions in cylindrical fuel-element end caps","authors":"Benjamin M. Ma","doi":"10.1016/0369-5816(65)90146-8","DOIUrl":"10.1016/0369-5816(65)90146-8","url":null,"abstract":"<div><p>The transient temperature distributions in bonded end caps of solid cylindrical fuel elements subjected to sudden change in temperature are determined analytically. The solution for the temperature distributions is expressed by products of Bessel functions, exponential functions and coupling relations between the end cap and the fuel section of the fuel element. A numerical example is given for enriched uranium oxide dispersed fuel elements with zircaloy cladding and bonded zircaloy end caps. From the calculated results of the example several conclusions are drawn (see section 4).</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 5","pages":"Pages 443-448"},"PeriodicalIF":0.0,"publicationDate":"1965-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90146-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90571983","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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