Nuclear Structural Engineering最新文献

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Mitteilung aus der arbeitsgruppe fur bautechnischen strahlenschutz an der technischen hochschule Hannover 防幅装置任务组在汉诺威技术学院发出的讯息
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90153-5
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引用次数: 0
Nondestructive testing of nuclear reactor components 核反应堆部件无损检测
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90149-3
Warren J. McGonnagle
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引用次数: 0
Investigation of large scale use of radioactive krypton-85 for leak detection in the Saturn space vehicle 大规模使用放射性氪-85用于土星空间飞行器泄漏检测的研究
Nuclear Structural Engineering Pub Date : 1965-05-01 DOI: 10.1016/0369-5816(65)90151-1
L.E. Brownell, M.A. Farvar, G.L. Gyorey, M. York
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引用次数: 3
Design of transitions for cylindrical reactor fuel element end caps 圆柱形反应堆燃料元件端盖过渡设计
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90016-5
Kenneth R. Merckx
{"title":"Design of transitions for cylindrical reactor fuel element end caps","authors":"Kenneth R. Merckx","doi":"10.1016/0369-5816(65)90016-5","DOIUrl":"10.1016/0369-5816(65)90016-5","url":null,"abstract":"<div><p>End closure design for reactor fuel elements must account for the transition in materials, geometry, and thermal conditions. In this paper, a method of analysis and numerical results are presented which apply to the designing of closures of cylindrical fuel elements. The significance and application to end cap design of the results of a series of parametric studies for bending and shear stresses in transitions having various heights, lengths, shapes, and thickness-to-radius ratios are discussed.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 360-367"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90016-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74450386","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 problem of prestressed concrete pressure vessels: Stress concentration adjacent to reinforced penetration under unidirectional stress 预应力混凝土压力容器的一个问题:单向应力作用下钢筋穿透附近的应力集中
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90019-0
A.N. Kinkead
{"title":"A problem of prestressed concrete pressure vessels: Stress concentration adjacent to reinforced penetration under unidirectional stress","authors":"A.N. Kinkead","doi":"10.1016/0369-5816(65)90019-0","DOIUrl":"10.1016/0369-5816(65)90019-0","url":null,"abstract":"<div><p>Present design philosophy for the advanced concept of the high temperature gas cooled reactor recommends easily removable and replaceable heat exchanger units which are enclosed within the prestressed concrete pressure vessel. This results in relatively large penetrations in the vessel wall becoming a prime requirement, because the openings required for heat exchanger withdrawal are of necessity much larger than those for the insertion of refuelling machines or control mechanisms.</p><p>The present paper deals with the simplest case likely to occur in practice, namely an individual circular opening in an infinitely wide slab of uniform thickness subjected to unidirectional stress in the plane of the slab. The theory presented assumes that the reinforcement to the penetration (i.e., the shutter tube) is bonded to the slab material and that both materials behave in a perfectly elastic manner. A further simplifying assumption made in the development of the theory is that the reinforcement material is concentrated along the edge of the opening in the slab. This to all intents and purposes is true for most practical values of reinforcement thickness. Allowance is made for the difference in elasticity between the materials of the slab and its reinforcement at the penetration.</p><p>The equations developed will apply equally well to a similar plane stress problem where there exists the combination of any two elastic materials bonded together at a circular opening. A part of the theory developed may be applied directly to the case of hydrostatic plane stress conditions in the slab in the region adjacent to such a circular reinforced penetration.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 395-402"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90019-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82507462","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
Shallow anisotropic plastic shells 浅各向异性塑料壳
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90021-9
M.Sh. Mikeladze
{"title":"Shallow anisotropic plastic shells","authors":"M.Sh. Mikeladze","doi":"10.1016/0369-5816(65)90021-9","DOIUrl":"10.1016/0369-5816(65)90021-9","url":null,"abstract":"<div><p>Equations describing the behaviour of shallow anisotropic plastic shells are derived. The treatment includes the problem of load carrying capacity and optimum (minimum volume) design. The material of the shell is assumed to be rigid-plastic and to obey Hill's yield condition and the associated flow rule.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 414-418"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90021-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82698680","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
Method for thermoviscoelastic stress analysis in concrete reactor vessels 混凝土反应堆容器热粘弹性应力分析方法
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90018-9
R.L. Taylor
{"title":"Method for thermoviscoelastic stress analysis in concrete reactor vessels","authors":"R.L. Taylor","doi":"10.1016/0369-5816(65)90018-9","DOIUrl":"10.1016/0369-5816(65)90018-9","url":null,"abstract":"<div><p>This paper is concerned with the analysis of problems in thermoviscoelasticity. The displacement equations of equilibrium governing the behavior of stressed, isotropic, thermorheologically simple materials subjected to thermal variations are formulated with respect to integral constitutive equations. This leads to a system of three, second order, variable coefficient, partial differential equations in the spatial coordinates and integral equations in the time. The general problem is formulated within the framework of classical, uncoupled thermoviscoelastic theory. A solution to the general displacement equations of equilibrium is presented for a point symmetric temperature field and point symmetric boundary conditions.</p><p>The general theory is also formulated from the principle of virtual displacements. From the principle of virtual displacements, it is shown how exact, as well as approximate, solutions may be obtained. An example is included for the solution to an incompressible hollow cylinder subjected to an axisymmetric temperature field.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 385-394"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90018-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90094777","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
Temperature distributions in end closures of annular fuel elements 环形燃料元件端盖内的温度分布
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90015-3
Benjamin M. Ma
{"title":"Temperature distributions in end closures of annular fuel elements","authors":"Benjamin M. Ma","doi":"10.1016/0369-5816(65)90015-3","DOIUrl":"10.1016/0369-5816(65)90015-3","url":null,"abstract":"<div><p>The temperature distributions in bonded end closures of annular fuel elements, such as those often used in nuclear superheating power reactors, are determined analytically. The solution for the temperature distributions is represented by products of the Bessel functions with hyperbolic functions. An illustrative example is that for enriched uranium oxide and plutonium oxide (UO<sub>2</sub>.PuO<sub>2</sub>) fuel with zircaloy-4 cladding and end closures in an inner (or central) superheating fast-reactor core. The assumed lengths of the end closure are 0.1, 0.5, 1.0 and 1.5 times the outer radius of the fuel element. The calculated results of the example indicate that </p><ul><li><span>1.</span><span><p>1. the temperature distributions in the end closures approach constants as the lengths of the end closures increase;</p></span></li><li><span>2.</span><span><p>2. there is an optimum length of end closure for each fuel element design; further increase in its length will waste the end-closure material;</p></span></li><li><span>3.</span><span><p>3. the temperature distribution in the thin end closures is approximately linear.</p></span></li><li><span>4.</span><span><p>4. to maintain the integrity of fuel elements, surface temperatures of cladding and end closures of the fuel elements must be kept appreciably below the known corrosion temperature limit of the coolant.</p></span></li></ul></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 353-359"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90015-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76360322","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
An experimental study on the burst strength of fuel cladding tubes under loss of coolant accident conditions in water cooled power reactors 水冷堆失冷剂事故条件下燃料包壳管爆裂强度的实验研究
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90022-0
Y. Mishima , I. Katsura, K. Ono, H. Tanaka, S. Wakisaka, M. Kosaki, Z. Takao, M. Toyoda, M. Yokosuka
{"title":"An experimental study on the burst strength of fuel cladding tubes under loss of coolant accident conditions in water cooled power reactors","authors":"Y. Mishima ,&nbsp;I. Katsura,&nbsp;K. Ono,&nbsp;H. Tanaka,&nbsp;S. Wakisaka,&nbsp;M. Kosaki,&nbsp;Z. Takao,&nbsp;M. Toyoda,&nbsp;M. Yokosuka","doi":"10.1016/0369-5816(65)90022-0","DOIUrl":"10.1016/0369-5816(65)90022-0","url":null,"abstract":"<div><p>Experimental study has been carried out on the burst strength of fuel cladding tubes of stainless steel and zircaloy under simulated loss-of-coolant accidents in water-cooled power reactors. The results of high-temperature tensile tests and high-temperature burst tests conducted under static and dynamic loading conditions are analysed. The effect of absorbed hydrogen on the mechanical properties of the tubes is investigated.</p></div>","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 419-437"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90022-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88561797","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
Discussion on: “Vorschlag fur ein systematisches bewertungsverfahren zur wahl von reaktorstandorten” by H. Luks 查明《关于选择反应堆的系统评估程序
Nuclear Structural Engineering Pub Date : 1965-04-01 DOI: 10.1016/0369-5816(65)90024-4
P. Courvoisier
{"title":"Discussion on: “Vorschlag fur ein systematisches bewertungsverfahren zur wahl von reaktorstandorten” by H. Luks","authors":"P. Courvoisier","doi":"10.1016/0369-5816(65)90024-4","DOIUrl":"10.1016/0369-5816(65)90024-4","url":null,"abstract":"","PeriodicalId":100973,"journal":{"name":"Nuclear Structural Engineering","volume":"1 4","pages":"Pages 440-441"},"PeriodicalIF":0.0,"publicationDate":"1965-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0369-5816(65)90024-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"108163663","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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