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Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology最新文献

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Diffusion of uranium in molybdenum, niobium, zirconium and titanium 铀在钼、铌、锆和钛中的扩散
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90144-3
L. V. Pavlinov, A. I. Nakonechnikov, V. N. Bykov
{"title":"Diffusion of uranium in molybdenum, niobium, zirconium and titanium","authors":"L. V. Pavlinov, A. I. Nakonechnikov, V. N. Bykov","doi":"10.1016/0368-3230(66)90144-3","DOIUrl":"https://doi.org/10.1016/0368-3230(66)90144-3","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"29 1","pages":"1027-1030"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79006702","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
Steady-state neutron spectra in beryllium 铍的稳态中子谱
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90135-2
P.S. Grover, F. Ahmed
{"title":"Steady-state neutron spectra in beryllium","authors":"P.S. Grover, F. Ahmed","doi":"10.1016/0368-3230(66)90135-2","DOIUrl":"10.1016/0368-3230(66)90135-2","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 979-981"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90135-2","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84332840","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
Physics of nuclear reactors 核反应堆物理学
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90137-6
J.F. Hill
{"title":"Physics of nuclear reactors","authors":"J.F. Hill","doi":"10.1016/0368-3230(66)90137-6","DOIUrl":"10.1016/0368-3230(66)90137-6","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Page 985"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90137-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"93029591","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
Use of the Pn approximation to describe the neutron distribution in an absorbing rod 用Pn近似来描述吸收棒中的中子分布
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90139-X
I. V. Sergeev
{"title":"Use of the Pn approximation to describe the neutron distribution in an absorbing rod","authors":"I. V. Sergeev","doi":"10.1016/0368-3230(66)90139-X","DOIUrl":"https://doi.org/10.1016/0368-3230(66)90139-X","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"3 1","pages":"987-992"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79487307","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
Asymptotic solutions in transport theory part I—One velocity with isotropic scattering☆ 输运理论的渐近解。第一部分:具有各向同性散射的速度
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90131-5
A. Ghatak, F. Ahmed
{"title":"Asymptotic solutions in transport theory part I—One velocity with isotropic scattering☆","authors":"A. Ghatak, F. Ahmed","doi":"10.1016/0368-3230(66)90131-5","DOIUrl":"https://doi.org/10.1016/0368-3230(66)90131-5","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"39 1","pages":"939-951"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86985767","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
Arbitrary division of space and angular variables in solving the neutron transport equation 求解中子输运方程中空间和角变量的任意划分
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90153-4
V.V. Khromov, I.S. Slesarev
{"title":"Arbitrary division of space and angular variables in solving the neutron transport equation","authors":"V.V. Khromov, I.S. Slesarev","doi":"10.1016/0368-3230(66)90153-4","DOIUrl":"https://doi.org/10.1016/0368-3230(66)90153-4","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 1056-1059"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90153-4","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91685184","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
The effect of a black sphere on the flux distribution in an infinite moderator 黑球对无限慢化剂中通量分布的影响
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90129-7
D.C. Sahni
{"title":"The effect of a black sphere on the flux distribution in an infinite moderator","authors":"D.C. Sahni","doi":"10.1016/0368-3230(66)90129-7","DOIUrl":"https://doi.org/10.1016/0368-3230(66)90129-7","url":null,"abstract":"<div><p>The method of singular integral equations has been applied to obtain the monoenergetic flux distribution due to a black sphere in an infinite, absorption-free and isotropically scattering moderator. The linear extrapolation distances have been obtained from these calculations and compared with the variational calculations.</p></div>","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 915-920"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90129-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90124938","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: 36
The use of concrete for shielding high-temperature reactors 用混凝土屏蔽高温反应堆
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90145-5
V.B. Dubrovskii, N.V. Krasnoyarov, M.Ya. Kulakovskii, B.K. Pergamenshchik, M.S. Pinkhasik, V.I. Savitskii
{"title":"The use of concrete for shielding high-temperature reactors","authors":"V.B. Dubrovskii,&nbsp;N.V. Krasnoyarov,&nbsp;M.Ya. Kulakovskii,&nbsp;B.K. Pergamenshchik,&nbsp;M.S. Pinkhasik,&nbsp;V.I. Savitskii","doi":"10.1016/0368-3230(66)90145-5","DOIUrl":"10.1016/0368-3230(66)90145-5","url":null,"abstract":"<div><p>The possibility is examined of constructing thermal shields of reactors from chromite and fireclay heat-resistant concretes. Neutron fluxes of different intensities (up to 10<sup>13</sup> n/cm<sup>2</sup> sec, close in spectrum to the fission spectrum) absorbed by shields of these materials are examined. The passage of neutrons, y-ray fluxes and generation of heat in the shield are taken into account. The temperatures in the shield are calculated for different neutron fluxes, thicknesses of concrete and cooling conditions. A static calculation of the temperature stresses in a shield constructed from heat-proof reinforced concrete is carried out.</p><p>It is established that heat-resistant reinforced concrete can be used for the shields of nuclear reactors for neutron fluxes to the concrete up to 10<sup>13</sup> n/cm<sup>2</sup> sec, temperatures up to 1000–1100°C and temperature drops of up to 900°C.</p></div>","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 1031-1038"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90145-5","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91525949","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
An electrophoretic filter for purifying reactor water 用于净化反应堆水的电泳过滤器
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90140-6
V.D. Ganzha, A.I. Egorov, D.M. Kaminker, A.V. Kolyadin, K.A. Konoplev, Yu.A. Saikov, V.T. Sharov
{"title":"An electrophoretic filter for purifying reactor water","authors":"V.D. Ganzha,&nbsp;A.I. Egorov,&nbsp;D.M. Kaminker,&nbsp;A.V. Kolyadin,&nbsp;K.A. Konoplev,&nbsp;Yu.A. Saikov,&nbsp;V.T. Sharov","doi":"10.1016/0368-3230(66)90140-6","DOIUrl":"10.1016/0368-3230(66)90140-6","url":null,"abstract":"<div><p>As the result of corrosion there formed in the water of the main circuit of the reactor of the A.F. loffe Physico-technical Institute of the Academy of Sciences of the U.S.S.R. a hydrate of alumina that was difficult to dissolve. An electrophoretic filter of special design made it possible to clean the coolant of the main circuit completely. The filter has a total capacity of 10·7 l., its hydraulic resistance is low, and it is easy to service. The effective discharge through the filter is 0·5 m<sup>3</sup>/hr. The power employed is 0·3 kW.</p></div>","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 993-999"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90140-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78558682","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
Asymptotic solution of the kinetic equation and diffusion characteristics ( 动力学方程及扩散特性的渐近解(
Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-11-01 DOI: 10.1016/0368-3230(66)90146-7
Ya.I. Granovskii, A.A. Kostritsa
{"title":"Asymptotic solution of the kinetic equation and diffusion characteristics (","authors":"Ya.I. Granovskii,&nbsp;A.A. Kostritsa","doi":"10.1016/0368-3230(66)90146-7","DOIUrl":"https://doi.org/10.1016/0368-3230(66)90146-7","url":null,"abstract":"","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 1039-1043"},"PeriodicalIF":0.0,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90146-7","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90027729","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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