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AbstractAbstract
No abstract available
Original Title
Novye dannye po strukture i diagnostike tregerita i vodorodnogo uranospinita
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Journal Article
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Dokl. Akad. Nauk SSSR, Mineral; v. 197(1); p. 178-181
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AbstractAbstract
No abstract available
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Journal Article
Journal
Journal of Inorganic and Nuclear Chemistry; v. 34(2); p. 531-534
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Notley, M.J.F.; Pettigrew, M.J.; Vidal, H.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs
AbstractAbstract
No abstract available
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Source
Jan 1972; 24 p; 16 refs.
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Report
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Madhusudana, C.V.
Fifth AINSE heat transfer and fluid flow conference, 23rd and 24th August 1971 - at Lucas Heights
Fifth AINSE heat transfer and fluid flow conference, 23rd and 24th August 1971 - at Lucas Heights
AbstractAbstract
No abstract available
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Secondary Subject
Source
Australian Inst. of Nuclear Science and Engineering, Lucas Heights; p. 36; 1971; 5. AINSE heat transfer and fluid flow conference; Lucas Heights, Australia; 23 Aug 1971; Abstract only.
Record Type
Report
Literature Type
Conference
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Silva, T.M. da.
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
AbstractAbstract
[en] Published in summary form only
Original Title
Contribuicao ao estudo da nova filosofia internacional de seguranca radiologica no processamento quimico do uranio natural
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Source
1990; 1 p
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Miscellaneous
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AbstractAbstract
[en] This Safety Analysis Report - Packages (SARP) documents compliance of the package design, construction methods, material and test performance with Specification 7A, type A packaging regulations
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Jun 1984; 34 p; Available from NTIS, PC A03/MF A01 as DE85007912
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Report
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AbstractAbstract
[en] Thermal shock behavior of UO2 pellets has been investigated by means of out-of-pile experiments and a theoretical analysis which particularly emphasized the porosity effect on the thermal shock damage. In the experiments, specimens of porosity range 0.05-0.15 were thermal-shocked by heating and then quenching in a water bath at various quenching temperature differences (ΔT). Results showed that with increasing porosity, ΔT values cause a first damage (ΔTsub(c)) and bring about destructive failure of the specimens increased, while the strength loss at ΔTsub(c) was reduced. These findings suggested that the higher the porosity, the higher the pellet integrity during rise to power. Theoretical equations expressing the thermal shock damage were introduced. Good agreements were obtained between observed and predicted values. (orig.)
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Journal Article
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Journal of Nuclear Materials; ISSN 0022-3115; 
; v. 127(1); p. 67-76
; v. 127(1); p. 67-76
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AbstractAbstract
[en] Ammonium diuranate U2O7(NH4)2 containing about 50% of water is dried and transformed by calcination in uranium trioxide UO3. Drying and calcination was obtained by air heated by two burners using domestic fuel. In 1984 the plant was transformed for utilization of electric heating improving maintenance cost, decreasing heat losses and by energy saving the payback period on investment is of 2.6 years
[fr]
Le diuranate d'ammonium U207(NH4)2, contenant environ 50% de son poids d'eau est seche dans un presecheur a tablier, puis transforme en trioxyde d'uranium (UO3) dans un calcinateur a bande perforee. Le sechage calcination etait assure par de l'air chauffe au moyen de 2 bruleurs a fioul domestique. L'installation electrique mise en service en 1984 a permis d'ameliorer les couts d'entretien, de diminuer les pertes de chaleur et d'economiser l'energie, le temps de retour des investissements est de 2,6 anneesOriginal Title
Chauffage electrique d'une unite de production de trioxyde d'uranium
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Journal Article
Journal
JFE. Journal Francais de l'Electrothermie; ISSN 0758-9735; ; (no.5); p. 39-41
; (no.5); p. 39-41
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AbstractAbstract
[en] Short communication
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Source
International Atomic Energy Agency, Vienna (Austria); Technical reports series; No. 12; 363 p; Nov 1962; p. 21-23; IAEA; Vienna (Austria); Panel on light water lattices; Vienna (Austria); 28 May - 1 Jun 1962
Record Type
Book
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Conference
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Hart, J.E.; Shuck, D.L.; Lyon, W.L.
Westinghouse Electric Corp., Pittsburgh, PA (USA)
Westinghouse Electric Corp., Pittsburgh, PA (USA)
AbstractAbstract
[en] The description is given of a process for converting uranium hexafluoride UF6 into uranium oxide powder of ceramic grade having a residual fluoride level, in fluidised bed reactors. A mixture essentially comprising uranium hexafluoride and steam (H2O) at the rate of 2 to 8 moles of steam per mole of uranium is introduced into a first fluidised bed reactor maintained at a temperature of 475 to 6000C to produce an initial intermediate reaction product comprising solid particles of uranyl fluoride UO2F2 and oxide U3O8 and a by-product gas including hydrofluoric acid HF. The first solid product from the intermediate reaction is sent to a second fluidised bed reactor where the molar fraction of hydrofluoric acid is adjusted so as to minimise the formation of uranium tetrafluoride UF4 by introducing extra steam and hydrogen into the second fluidised bed at the rate of 4 to 12 moles of steam and 1 to 6 moles of hydrogen per mole of uranium, whilst this second bed is maintained at between 575 and 6750C to produce a second intermediate reaction product comprising uranium dioxide UO2
[fr]
On decrit un procede pour convertir dans des reacteurs a lit fluidise de l'hexafluorure d'uranium UF6 en poudre d'oxyde d'uranium de qualite ceramique ayant une faible teneur en fluorure residuel. Un melange comprenant essentiellement de l'hexafluorure d'uranium et de la vapeur (H2O) a raison de 2 a 8 moles de vapeur par mole d'uranium, est introduit dans un premier reacteur a lit fluidise maintenu a une temperature de 475 a 6000C pour produire un premier produit de reaction intermediaire comprenant des particules solides de fluorure d'uranyle UO2F2 et d'oxyde U3O8 et un gaz sous produit comprenant de l'acide fluorhydrique HF. Le premier produit solide de reaction intermediaire est dirige vers un deuxieme reacteur a lit fluidise dans lequel la fraction molaire d'acide fluorhydrique est regulee de facon a minimiser la formation du tetrafluorure d'uranium UF4 par l'introduction dans le deuxieme lit fluidise de vapeur et d'hydrogene supplementaires a raison de 4 a 12 moles de vapeur et de 1 a 6 moles d'hydrogene par mole d'uranium, tandis que ce deuxieme lit est maintenu a une temperature comprise entre 575 et 6750C pour produire un deuxieme produit de reaction intermediaire comprenant du bioxyde d'uranium UO2Original Title
Production de bioxyde d'uranium
Primary Subject
Source
13 Jun 1977; 23 p; FR PATENT DOCUMENT 2355359/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 14 Jun 1976, US.
Record Type
Patent
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