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

The Effect of Neutron Irradiation On The Structure And Properties Of Low-Carbon Alloy Steels 中子辐照对低碳合金钢组织和性能的影响

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30041-9

V.S. Liashenko, S.S. Ibragimov

引用次数: 1

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30034-1

J.B. Sykes

引用次数: 0

The Solubility Of Metals In Liquid Metals 金属在液态金属中的溶解度

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30031-6

D.H. Kerridge

引用次数: 4

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30040-7

B.G. Chapman

引用次数: 0

Some Reactions Between Thorium Oxide And Inhibited Heavy Liquid Metals 氧化钍与抑制重金属之间的一些反应

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30032-8

G.H. Broomfield, J.M. Matthews, A. Bartlett

{"title":"Some Reactions Between Thorium Oxide And Inhibited Heavy Liquid Metals","authors":"G.H. Broomfield, J.M. Matthews, A. Bartlett","doi":"10.1016/S0368-3273(15)30032-8","DOIUrl":"10.1016/S0368-3273(15)30032-8","url":null,"abstract":"<div><p>As part of a study of liquid metal slurries as blanket materials for liquid metal fuelled reactors, thoria prepared by calcination of the oxalate has been mixed vigorously with inhibited lead, lead-bismuth eutectic and bismuth at temperatures in the range 500-600°C to form slurries containing up to 18 per cent (by volume) solids. Solidified samples have been examined for reactions between the corrosion inhibitors (zirconium and magnesium) and thoria, immediately after preparation and after circulation in thermal convection loops and in a pumped loop.</p><p>Magnesium at eutectic concentration in lead and bismuth reacted with thoria to produce intermetallic compounds which plugged thermal convection loops. Magnesium at normal inhibitor levels did not reduce thoria to give a thorium concentration in excess of the solubility limit in bismuth at 400°C.</p><p>Thoria concentrations of up to 7 per cent in bismuth were not found to effect the rheological properties of the liquids in these experiments, nor to alter corrosion inhibition effects by the ZrN film technique. The rheology of lead slurries was influenced principally by thoria settling upwards. Apart from settling effects the slurries were physically stable.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30032-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82032870","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 Design and Development of Pumps for Sodium and Sodium-Potassium Alloys 钠和钠钾合金泵的设计与开发

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30043-2

P.L. Kirillov, V.A. Kuznetsov, N.M. Turchin, Yu. M. Fedoseyev

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

引用次数: 0

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30036-5

J.P. Howe

引用次数: 0

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30035-3

D.H. Fax

引用次数: 0

A Method of Predicting the Critical Mass and Neutron Flux Distribution of a Reactor by Use of a Physical Model 用物理模型预测反应堆临界质量和中子通量分布的方法

Journal of Nuclear Energy. Part B. Reactor Technology Pub Date : 1961-01-01 DOI: 10.1016/S0368-3273(15)30044-4

V.A. Dmitrievskii, I.S. Grigor'ev

{"title":"A Method of Predicting the Critical Mass and Neutron Flux Distribution of a Reactor by Use of a Physical Model","authors":"V.A. Dmitrievskii, I.S. Grigor'ev","doi":"10.1016/S0368-3273(15)30044-4","DOIUrl":"10.1016/S0368-3273(15)30044-4","url":null,"abstract":"<div><p>The detailed design of a nuclear reactor, especially if it is of a new type, must be preceded by experimental work to refine the calculated parameters. A new method is proposed for determining the critical mass and the neutron flux distribution. A model of the reactor is used that is free from fissile material. The fuel channels are filled with a neutron absorber, of cross-section equivalent to that of the intended fuel, and the creation of fast fission neutrons is simulated by a neutron source which is moved along the various channels in turn. Resulting thermal neutron flux distributions are measured with thermal neutron detectors. The required critical mass can be deduced if the absolute source strength and neutron flux are known. The method has been checked on a reactor that operates with uranium hexafluoride. A critical mass was predicted that was in good agreement with the value found on starting up the reactor. The method may be of use in preliminary studies of new reactors in assisting in the choice of lattice dimensions and other parameters. It is simple, and involves neither fissile materials nor high neutron fluxes.</p></div>","PeriodicalId":100814,"journal":{"name":"Journal of Nuclear Energy. Part B. Reactor Technology","volume":null,"pages":null},"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)30044-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84932119","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