Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30055-9
{"title":"Notice","authors":"","doi":"10.1016/S0368-3273(15)30055-9","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30055-9","url":null,"abstract":"","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)30055-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"137165638","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30039-0
L.J. Koch
{"title":"","authors":"L.J. Koch","doi":"10.1016/S0368-3273(15)30039-0","DOIUrl":"10.1016/S0368-3273(15)30039-0","url":null,"abstract":"","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)30039-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91210697","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30042-0
P.S. Sliusarev, V.A. Ivanov, L.N. Nesterova
A study has been made of the rate at which the corrosion products of 1Kh18N9T steel are flushed out by the water coolant in the First Nuclear Power Station. It was established that the rate depends on the power level and on the rate at which water is added to the first loop. Radiation from the reactor causes oxidation of dissolved nitrogen to nitric acid. The nature of the corrosion products has been studied by ion exchange, electrodialysis, ultrafiltration, spectroscopic and chemical analysis, and radiation measurement. It has been shown that all corrosion products of 1Kh18N9T steel, with the exception of iron, are present as ions.
{"title":"Contaminants In The Water-Cooling Circuit Of The First Nuclear Power Station","authors":"P.S. Sliusarev, V.A. Ivanov, L.N. Nesterova","doi":"10.1016/S0368-3273(15)30042-0","DOIUrl":"10.1016/S0368-3273(15)30042-0","url":null,"abstract":"<div><p>A study has been made of the rate at which the corrosion products of 1Kh18N9T steel are flushed out by the water coolant in the First Nuclear Power Station. It was established that the rate depends on the power level and on the rate at which water is added to the first loop. Radiation from the reactor causes oxidation of dissolved nitrogen to nitric acid. The nature of the corrosion products has been studied by ion exchange, electrodialysis, ultrafiltration, spectroscopic and chemical analysis, and radiation measurement. It has been shown that all corrosion products of 1Kh18N9T steel, with the exception of iron, are present as ions.</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)30042-0","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"102332267","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30038-9
E. Bretscher
{"title":"","authors":"E. Bretscher","doi":"10.1016/S0368-3273(15)30038-9","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30038-9","url":null,"abstract":"","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)30038-9","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"137436293","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30050-X
E.A. Mitkina
{"title":"Measurement of the specific heats of uranium, thorium and other metals","authors":"E.A. Mitkina","doi":"10.1016/S0368-3273(15)30050-X","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30050-X","url":null,"abstract":"","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)30050-X","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90001113","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}
{"title":"The effect of an internal heat source on the heat-transfer coefficient","authors":"S.S. Kutateladze, N.I. Ivashchenko, T.V. Zablotskaya","doi":"10.1016/S0368-3273(15)30046-8","DOIUrl":"10.1016/S0368-3273(15)30046-8","url":null,"abstract":"","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)30046-8","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"111465942","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30045-6
I.V. Batenin, A.N. Rudenko, B.V. Sharov
A new growth process is described in which uranium specimens increase in length when they are held at an elevated temperature in air, nitrogen or carbon dioxide. The dependence of this growth on temperature, the pressure of the gas, the diameter of the rods and also on the presence of previously formed oxide layers was determined. Growth of copper wire specimens was also found to occur. A possible mechanism for the growth of uranium rods is postulated.
{"title":"The Growth of Uranium Rods in Corrosive Atmospheres","authors":"I.V. Batenin, A.N. Rudenko, B.V. Sharov","doi":"10.1016/S0368-3273(15)30045-6","DOIUrl":"10.1016/S0368-3273(15)30045-6","url":null,"abstract":"<div><p>A new growth process is described in which uranium specimens increase in length when they are held at an elevated temperature in air, nitrogen or carbon dioxide. The dependence of this growth on temperature, the pressure of the gas, the diameter of the rods and also on the presence of previously formed oxide layers was determined. Growth of copper wire specimens was also found to occur. A possible mechanism for the growth of uranium rods is postulated.</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)30045-6","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77178731","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30049-3
V.I. Petrovichev
{"title":"Heat transfer for mercury flowing in annular channels","authors":"V.I. Petrovichev","doi":"10.1016/S0368-3273(15)30049-3","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30049-3","url":null,"abstract":"","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)30049-3","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90001111","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30051-1
N.I. Buleev
{"title":"A numerical method for the solution of two-dimensional diffusion equations","authors":"N.I. Buleev","doi":"10.1016/S0368-3273(15)30051-1","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30051-1","url":null,"abstract":"","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)30051-1","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90001112","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}
Pub Date : 1961-01-01DOI: 10.1016/S0368-3273(15)30050-X
E. A. Mitkina
{"title":"Measurement of the specific heats of uranium, thorium and other metals","authors":"E. A. Mitkina","doi":"10.1016/S0368-3273(15)30050-X","DOIUrl":"https://doi.org/10.1016/S0368-3273(15)30050-X","url":null,"abstract":"","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":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74266195","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}
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