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

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A numerical method for the solution of two-dimensional diffusion equations‡ 二维扩散方程的一种数值解法
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30051-1
N. I. Buleev
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引用次数: 1
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30037-7
H.E. Vann
{"title":"","authors":"H.E. Vann","doi":"10.1016/S0368-3273(15)30037-7","DOIUrl":"10.1016/S0368-3273(15)30037-7","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 4","pages":"Pages 239-240"},"PeriodicalIF":0.0,"publicationDate":"1961-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30037-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80092783","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-induced changes in some physical properties of graphites of various degrees of graphitization 辐射引起不同程度石墨化石墨的某些物理性质的变化
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30053-5
Iu N. Aleksenko, L.E. Kakushadze
{"title":"Radiation-induced changes in some physical properties of graphites of various degrees of graphitization","authors":"Iu N. Aleksenko, L.E. Kakushadze","doi":"10.1016/S0368-3273(15)30053-5","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30053-5","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 4","pages":"Pages 272-273"},"PeriodicalIF":0.0,"publicationDate":"1961-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30053-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90001115","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
Forces Between Slurry Particles Due To Surface Tension 由于表面张力，浆料颗粒之间的力
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30033-X
J. Woodrow, H. Chilton , R.I. Hawes
{"title":"Forces Between Slurry Particles Due To Surface Tension","authors":"J. Woodrow,&nbsp;H. Chilton ,&nbsp;R.I. Hawes","doi":"10.1016/S0368-3273(15)30033-X","DOIUrl":"10.1016/S0368-3273(15)30033-X","url":null,"abstract":"<div><p>Equations are derived defining the shape of small bubbles or drops which may form between pairs of slurry particles, immersed in a liquid vehicle; the system considered is axially symmetric. The resultant bubble or drop shapes are also presented graphically.</p><p>The force which a bubble or drop may transmit between particles is derived and evaluated for some particular cases of interest.</p><p>In a system with only two components, any bubble must contain the vapour phase of the liquid vehicle, at reduced pressure. Such a bubble can only exist if the contact angle, measured in the liquid phase, exceeds 90° and it will always exert a cohesive force, holding the slurry particles in contact.</p><p>Three component systems can be formed with bubbles or immiscible liquid drops joining adjacent slurry particles, provided that the contact angle is greater than zero, and they may transmit a cohesive force. This was demonstrated qualitatively by experiments with glass particles in water which flocculated heavily when shaken in air and dispersed when de-aerated, or when the contact angle was reduced to zero.</p><p>When a liquid metal slurry is exposed to neutron irradiation, gas may be generated, and may cause flocculation by this mechanism. Degassing may prove to be difficult.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 4","pages":"Pages 229-237, IN2-IN3"},"PeriodicalIF":0.0,"publicationDate":"1961-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30033-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73861523","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: 13
Heat transfer between a stream of molten sodium and a single cylinder lying across the direction of flow 熔融钠流与横过流动方向的单个圆柱体之间的热传递
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30047-X
A.A. Andreyevskii
{"title":"Heat transfer between a stream of molten sodium and a single cylinder lying across the direction of flow","authors":"A.A. Andreyevskii","doi":"10.1016/S0368-3273(15)30047-X","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30047-X","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 4","pages":"Pages 263-264"},"PeriodicalIF":0.0,"publicationDate":"1961-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30047-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91630674","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 generalized expression for critical heat flux 临界热通量的广义表达式
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30048-1
I. I. Novikov
{"title":"A generalized expression for critical heat flux","authors":"I. I. Novikov","doi":"10.1016/S0368-3273(15)30048-1","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30048-1","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"17 1","pages":"264-265"},"PeriodicalIF":0.0,"publicationDate":"1961-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75017914","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
Dilatometric studies of rolled uranium rods 轧制铀棒的膨胀学研究
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30052-3
I.V. Batenin, A.N. Rudenko, B.V. Sharov
{"title":"Dilatometric studies of rolled uranium rods","authors":"I.V. Batenin,&nbsp;A.N. Rudenko,&nbsp;B.V. Sharov","doi":"10.1016/S0368-3273(15)30052-3","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30052-3","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 4","pages":"Pages 271-272"},"PeriodicalIF":0.0,"publicationDate":"1961-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30052-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90001116","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 Determination of Xenon in Liquid Bismuth 液态铋中氙的测定
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30019-5
G.F. Hewitt, J.A. Lacey, E. Lyall
{"title":"The Determination of Xenon in Liquid Bismuth","authors":"G.F. Hewitt,&nbsp;J.A. Lacey,&nbsp;E. Lyall","doi":"10.1016/S0368-3273(15)30019-5","DOIUrl":"10.1016/S0368-3273(15)30019-5","url":null,"abstract":"<div><p>This paper describes the development of a method for estimating the concentration of xenon in molten bismuth.</p><p>A direct volumetric method and a technique employing gas thermal conductivity measurement were attempted and found unsatisfactory. A successful technique was developed involving the mass-spectrographic analysis of a hydrogen sample containing the xenon extracted from the bismuth, giving a sensitivity approaching 2 × 10<sup>−9</sup> atom Xe per atom Bi.</p><p>The latter method was applied to the determination of the solubility of xenon in bismuth at 500°C. It was found that the solubility was probably below the limit of sensitivity although there were some higher results.</p><p>A radioactive technique was employed to demonstrate that the solubility was actually below 2 × 10<sup>−10</sup> atomic fraction. The high degree of surface adsorption was demonstrated using an autoradiographic technique.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 3","pages":"Pages 167-172"},"PeriodicalIF":0.0,"publicationDate":"1960-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30019-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75119893","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
Stability Constants of Nitrato Complexes of Trivalent Plutonium in Aqueous and Tributyl Phosphate Solutions 三价钚硝酸配合物在水溶液和磷酸三丁酯溶液中的稳定性常数
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30030-4
V.B. Shevchenko, V.G. Timoshev, A.A. Volkova
{"title":"Stability Constants of Nitrato Complexes of Trivalent Plutonium in Aqueous and Tributyl Phosphate Solutions","authors":"V.B. Shevchenko,&nbsp;V.G. Timoshev,&nbsp;A.A. Volkova","doi":"10.1016/S0368-3273(15)30030-4","DOIUrl":"10.1016/S0368-3273(15)30030-4","url":null,"abstract":"<div><p>This paper deals with the extraction of nitrato complexes of trivalent plutonium from aqueous phases of various compositions. It is shown that Pu(III) is extracted by tributyl phosphate (TBP) from nitric acid solutions as Pu(NO<sub>3</sub>)<sub>3</sub>.TBP up to a nitrate ion concentration of 1·2 M. The distribution coefficient of Pu(III) is practically independent of the hydrogen ion concentration under the conditions studied. The stability constants of Pu(NO3)<sub>3</sub>.3TBP, Pu(NO<sub>3</sub>)<sub>3</sub>, Pu(NO<sub>3</sub>)<sub>2</sub><sup>+</sup> and Pu(NO<sub>3</sub>)<sub>2</sub><sup>+</sup> have been determined as 0·75 ± 0·1, 14·4 ± 0·8 and 5·9 + 0·5, respectively.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 3","pages":"Pages 211-214"},"PeriodicalIF":0.0,"publicationDate":"1960-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30030-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85124192","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
Experimental Test of the Theory of Neutron Diffusion in a Medium Containing Cavities 含腔介质中中子扩散理论的实验验证
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30028-6
I.F. Zhezherun
{"title":"Experimental Test of the Theory of Neutron Diffusion in a Medium Containing Cavities","authors":"I.F. Zhezherun","doi":"10.1016/S0368-3273(15)30028-6","DOIUrl":"10.1016/S0368-3273(15)30028-6","url":null,"abstract":"<div><p>Neutron fluxes have been measured in a solid graphite stack and in a stack with channels to test the theory of neutron diffusion. The results confirm the theoretical formulae relating the effective diffusion coefficients and diffusion lengths in a medium with empty channels to the channel parameters and to the corresponding diffusion coefficients and diffusion lengths for a continuous medium.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":"1 3","pages":"Pages 200-203"},"PeriodicalIF":0.0,"publicationDate":"1960-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/S0368-3273(15)30028-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91308049","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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