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

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Thoria as a Fertile Component for a Liquid Metal Breeder Blanket 钍作为液态金属增殖毯的可育成分
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30016-X
A. Brown, A. Chitty
{"title":"Thoria as a Fertile Component for a Liquid Metal Breeder Blanket","authors":"A. Brown,&nbsp;A. Chitty","doi":"10.1016/S0368-3273(15)30016-X","DOIUrl":"10.1016/S0368-3273(15)30016-X","url":null,"abstract":"<div><p>The crystal chemistry and physics of thoria are reviewed with emphasis on the properties required to form a stable suspension of thoria in liquid bismuth. The variation of the density of thoria with temperature has been determined accurately over the temperature range 0–1100°C and a measurement of the adsorbed gas (CO<sub>2</sub> and CO) has been made. It is shown that thoria is intrinsically wetted by bismuth provided the thoria surface is free from contamination. The solution of certain elements in the bismuth is shown to cause wetting of thoria produced by decomposition of thorium salts, and some elements are shown to reduce thoria with subsequent formation of ThBi<sub>2</sub>. A suspension of thoria in liquid bismuth containing an added element E is stable if the following relationship is satisfied: <span><math><mrow><mo>−</mo><mi>Δ</mi><msub><mi>G</mi><mrow><mi>o</mi><mi>x</mi></mrow></msub><mo>(</mo><mi>C</mi><mo>)</mo><mo>&lt;</mo><mo>−</mo><mi>Δ</mi><msub><mi>G</mi><mrow><mi>o</mi><mi>x</mi></mrow></msub><mo>(</mo><mi>E</mi><mo>)</mo><mo>&lt;</mo><mo>−</mo><mi>Δ</mi><msub><mi>G</mi><mrow><mi>o</mi><mi>x</mi></mrow></msub><mo>(</mo><mi>A</mi><mi>l</mi><mo>)</mo></mrow></math></span></p><p>The results are discussed in terms of the thermodynamics of oxidation/reduction processes.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30016-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78594384","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
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30022-5
C.M. Nicholls
{"title":"","authors":"C.M. Nicholls","doi":"10.1016/S0368-3273(15)30022-5","DOIUrl":"10.1016/S0368-3273(15)30022-5","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30022-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85248867","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
Temperature Distributions In Cylindrical Plain-Canned Fuel Elements Under Some Transient Conditions 一些瞬态条件下圆柱形普通罐装燃料元件的温度分布
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30018-3
R.E. Strickland, M. Angelopoulos
{"title":"Temperature Distributions In Cylindrical Plain-Canned Fuel Elements Under Some Transient Conditions","authors":"R.E. Strickland,&nbsp;M. Angelopoulos","doi":"10.1016/S0368-3273(15)30018-3","DOIUrl":"10.1016/S0368-3273(15)30018-3","url":null,"abstract":"<div><p>Two critical requirements in the design and operation of natural uranium reactors are the maintenance at all times of the maximum fuel temperature below 600°C, the phase change value and the limiting of the temperature of the can to a value such that its strength and corrosion-resistance properties are adequate. It is necessary, therefore, to examine temperature distributions in the fuel and can under possible significant transient conditions. Three such conditions are numerically examined using the experimental heat transfer data of HUGHES and SLACK (1958). In two cases, the temperature response to a step change in flux and to a typical flux control disturbance, the results show the time-lag effect due to the dominant time constant which has a characteristic value for each fuel-plus-can system. In the third case, the maximum temperature reached during fuel element charging under load is examined.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30018-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91468284","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
Losses Incurred in Turning a Gas Flowing in an Annular Duct Back into the Central Tube 将在环形管道中流动的气体转回中心管所造成的损失
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30020-1
F. Cheers
{"title":"Losses Incurred in Turning a Gas Flowing in an Annular Duct Back into the Central Tube","authors":"F. Cheers","doi":"10.1016/S0368-3273(15)30020-1","DOIUrl":"10.1016/S0368-3273(15)30020-1","url":null,"abstract":"<div><p>Tests have been carried out to determine the effect of the geometrical arrangement on the losses incurred in turning a fluid from an annular duct back into the central passage. It is shown that if the layout is well chosen, the losses need not be much greater than those for a sudden contraction of the same area ratio.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30020-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83964574","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
Calculation of the thermal conductivity of molten metals 熔融金属导热系数的计算
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30025-0
G.F. Butenko, M.I. Radchenko
{"title":"Calculation of the thermal conductivity of molten metals","authors":"G.F. Butenko,&nbsp;M.I. Radchenko","doi":"10.1016/S0368-3273(15)30025-0","DOIUrl":"10.1016/S0368-3273(15)30025-0","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30025-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84304410","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
Critical heat fluxes for water flowing in tubes 水在管内流动的临界热流密度
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30024-9
I.T. Aladiev, L.D. Dodonov, V.S. Udalov
{"title":"Critical heat fluxes for water flowing in tubes","authors":"I.T. Aladiev,&nbsp;L.D. Dodonov,&nbsp;V.S. Udalov","doi":"10.1016/S0368-3273(15)30024-9","DOIUrl":"10.1016/S0368-3273(15)30024-9","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30024-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87767404","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
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30023-7
L.C. Widdoes
{"title":"","authors":"L.C. Widdoes","doi":"10.1016/S0368-3273(15)30023-7","DOIUrl":"10.1016/S0368-3273(15)30023-7","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30023-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79263384","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
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30021-3
H.H. Yoshikawa
{"title":"","authors":"H.H. Yoshikawa","doi":"10.1016/S0368-3273(15)30021-3","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30021-3","url":null,"abstract":"","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30021-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"136714329","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 Pulsed Reactor 脉冲反应堆
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30026-2
T.N. Zubarev
{"title":"A Pulsed Reactor","authors":"T.N. Zubarev","doi":"10.1016/S0368-3273(15)30026-2","DOIUrl":"10.1016/S0368-3273(15)30026-2","url":null,"abstract":"<div><p>The design of a pulsed reactor using ordinary water and enriched uranium is presented together with a method of computing the physical and thermal parameters. Very stable heat production during the neutron bursts can be ensured, provided certain conditions are fulfilled. Calculations show that the suggested design can provide a thermal power of ≳5 MW with a mean neutron flux in the core ≳ 10<sup>14</sup> neutrons.cm<sup>−2</sup>. sec<sup>−1</sup> and a peak flux during the burst of about 10<sup>17</sup> neutrons.cm<sup>−2</sup>.sec<sup>−1</sup>.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30026-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80758077","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
Contact Angles between Liquid Bismuth and Pure Iron and Mild Steel. A Study of Interfacial Reactions 液态铋与纯铁和低碳钢的接触角。界面反应的研究
Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1960-01-01 DOI: 10.1016/S0368-3273(15)30017-1
D.H. Kerridge , S.D. Ford
{"title":"Contact Angles between Liquid Bismuth and Pure Iron and Mild Steel. A Study of Interfacial Reactions","authors":"D.H. Kerridge ,&nbsp;S.D. Ford","doi":"10.1016/S0368-3273(15)30017-1","DOIUrl":"10.1016/S0368-3273(15)30017-1","url":null,"abstract":"<div><p>The receding and advancing contact angles between liquid bismuth and pure iron and mild steel have been measured and the change of contact angle with time at a series of temperatures has been determined. Two chemical reactions have been found to take place at the solid-liquid interface. The first is thought to be the reaction of chloride ions (present as bismuth oxychloride impurity in the solution) with the iron surface; the second the reduction of bismuthyl ions by the iron. The first process has an activation energy of 30 kcal and the second process an activation energy of 15 kcal.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30017-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88908182","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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