AbstractAbstract
No abstract available
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Oct 1972; 10 p; 2. Italian-Polish meeting on some chemical, ceramic and metallurgic aspects of nuclear fuels; Rome, Italy; 3 Oct 1972
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Report
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Conference
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ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHEMICAL ANALYSIS, CHEMICAL REACTIONS, CONTROL, FUEL ELEMENTS, HEAVY WATER MODERATED REACTORS, HWLWR TYPE REACTORS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, THERMAL REACTORS, TIN ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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Baldetti, S.; Doria, F.; Gabaglio, M.; Grifoni, S.
Peaceful uses of atomic energy. Proceedings of the fourth international conference, jointly sponsored by the UN and the IAEA and held in Geneva, 6-16 September 1971. Vol. 91972
Peaceful uses of atomic energy. Proceedings of the fourth international conference, jointly sponsored by the UN and the IAEA and held in Geneva, 6-16 September 1971. Vol. 91972
AbstractAbstract
No abstract available
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United Nations, New York (USA); International Atomic Energy Agency, Vienna (Austria); Proceedings series; 15 v.; v. 9 p. 255-269; 1972; IAEA/UN; Vienna; 4. international conference on the peaceful uses of atomic energy; Geneva, Switzerland; 6 Sep 1971; A/CONF.49/P--186; Microfiche of preprint available from INIS Clearinghouse.
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Book
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Cogliati, G.; De Leone, R.; Ferrari, S.; Gabaglio, M.; Liscia, A.
New Nuclear Materials Including Non Metallic Fuel Elements. Vol. I. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements1963
New Nuclear Materials Including Non Metallic Fuel Elements. Vol. I. Proceedings of the Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements1963
AbstractAbstract
[en] A method for the preparation of sintered bodies of thorium-uranium mixed oxide starting from a solution of thorium nitrate and uranyl nitrate was investigated. This method can be useful both in the fabrication of fuel elements and in the reprocessing of such type of materials. In the first step of the method, uranyl nitrate is reduced to uranium (IV) nitrate. As reducing agent, both gaseous hydrogen and formic acid are employed; urea is added to prevent the formation of nitrous acid, which catalyses the reoxidation of uranium (IV). As catalyst, both platinum and palladium can be employed. Data are given for a continuous process, in which formic acid and urea are added to the solution, which is then pre-heated and passed in a column packed with 1/8 in x 1/8 in alumina pellets, carrying 0.5 wt.% of platinum. The influence of flow rate, temperature, formic acid and urea concentration, as well as catalyst life and poisoning are studied. The second step in the method is the precipitation of an oxalate of thorium and uranium (IV). The influence of oxalic acid to thorium-uranium ratio, temperature, aging time on settling and filtering characteristics of the precipitate and on the ceramic properties of the obtained powders is reported. Firing was carried out both in reducing and oxidizing atmosphere. After preliminary tests, two standard procedures were set up for the fabrication of ceramic bodies, namely by cold pressing and sintering and by extrusion and sintering. The ability of the different powders to sinter was tested by both of the two standard methods. With some of the powders, densities higher than 95% of theoretical density were obtained; reproducibility tests were successfully carried out. (author)
[fr]
Les auteurs etudient une methode de preparation de melanges frittes d'oxydes de thorium et d'uranium a partir d'une solution de nitrate de thorium et de nitrate d'uranyle. Cette methode peut etre utile auessi bien pour la fabrication d'elements combustibles que pour le recyclage de matieres de ce genre. Le procede consiste tout d'abord a reduire le nitrate d'uranyle en nitrate d'uranium (IV). On utilise comme agents reducteurs de l'hydrogene gazeux et de l'acide formique; on ajoute de l'uree pour prevenir la formation d'acide nitreux qui catalyse la reoxydation de l'uranium (IV). On peut employer comme catalyseurs le platine et le palladium. Les auteurs donnent des indications sur un processus continu au cours duquel on ajoute de l'acide formique et de l'uree a la solution qui est ensuite rechauffee avant d' etre passee dans une colonne remplie de.pastilles d'a lumine de 3,17 x 3,17 mm contenant 0,5% en poids de platine. Ils fournissent egalement des renseignements sur l'influence du debit, de la temperature et de la concentration de l'acide formique et de l'uree, ainsi que sur la duree de vie du catalyseur et l'empoisonnement. La precipitation d'un oxalate de thorium et d'uranium(IV) constitue la deuxieme phase. Les auteurs mentionnent l'influence de l'acide oxalique sur le rapport thorium/uranium, ainsi que ce l le de la temperature et du vieillissement surtles caracteristiques de la precipitation et du filtrage et sur les proprietes ceramiques des poudres obtenues. La mise a feu a ete faite dans une atmosphere reductrice et dans une atmosphere oxydante. Ces essais preliminaires ont abouti a la mise au point de deux methodes normalisees pour la fabrication d'elements ceramiques, a savoir la methode du pressage a froid puis frittage et la methode par extrusion et frittage. L'aptitude au frittage des differentes poudres a fait l'objet d'essais selon les deux methodes susmentionnees. Avec certaines des poudres, on a obtenu des densites depassant 95% de la valeur theorique; des essais de reproductibilite ont ete concluants. (author)[es]
Los autores han estudiado un metodo para preparar cuerpos sinterizados, compuestos por una mezcla de oxido de torio y uranio, a partir de una solucion de nitrato de torio y de nitrato de uranilo. Este metodo puede ser de utilidad para la elaboracion de elementos combustibles y para la regeneracion de los mismos. En la primera fase del metodo, el nitrato de uranilo se reduce a nitrato de uranio (IV). Como agente reductor se emplea acido formico e hidrogeno gaseoso; se anade urea para impedir la formacion de acido nitroso, que cataliza la reoxidacion del uranio (IV). En calidad de catalizadores pueden emplearse platino y paladio. Se facilitan datos relativos a un proceso continuo, en el que el acido formico y la urea se afladan a la solucion, que seguidamente se precalienta y se hace pasar a traves de una columna rellena de pastillas de alumina de 3,17 x 3,17 mm, que contienen 0,5% en peso de platino. Se estudia la influencia de la velocidad de circulacion, temperatura, concentraciones de acido formico y de urea, asi como la duracion y el envenenamiento del catalizador. La segunda fase del metodo consiste en la precipitacion de oxalato de torio y uranio (IV). Se estudia la influencia de la razon acido oxalico torio-uranio, de la temperatura y del tiempo de envejecimiento sobre las caracteristicas de sedimentacion y de filtracion del precipitado y sobre las propiedades ceramicas de los polvos obtenidos. El calentamiento se ha efectuado tanto en atmosfera reductora como oxidante. Luego de ensayos preliminares, se han establecido dos procedimientos normales para la elaboracion de cuerpos ceramicos, a saber, por prensado en frio y sinterizacion y por extrusion y sinterizacion. Las propiedades de sinterizacion de los diferentes polvos se han ensayado por los dos procedimientos normales. Con algunos de los polvos se han obtenido densidades superiores al 95% del valor teorico; se han realizado con exito ensayos de reproductibilidad. (author)[ru]
Issledovan protsess izgotovleniya spechennykh izdelij iz smesi torievo-uranovykh okislov, nachinayushchijsya s rastvoreniya nitrata toriya i nitrata uranila. Ehtot protsess mozhet okazat'sya poleznym kak dlya izgotovleniya toplivnykh ehlementov, tak i dlya regeneratsii materialov takogo roda. Na pervoj stadii protsessa nitrat uranila vosstanavlivaetsya do nitrata urana (IV). V kachestve vosstanovitelya ispol'zuyutsya kak gazoobraznyj vodorod, tak i murav'inaya kislota; mochevina dobavlyaetsya dlya predotvrashcheniya obrazovaniya azotistoj kisloty, kotoraya uskoryaet povtornoe okislenie urana (IV). V kachestve katalizatora mogut primenyat'sya platina i palladij. Privodyatsya dannye dlya nepreryvnogo protsessa, v kotorom murav'inaya kislota i mochevina dobavlyayutsya k rastvoru, poslednij zatem podogrevaetsya i podaetsya v kolonku, zapolnennuyu alyuminievymi tabletkami razmerom 3,87 x 3,17 mm, 0,5% kotorykh sostavlyaet platina. Izucheny vliyaniya skorosti potoka, temperatury, kontsentratsii murav'inoj kisloty i mocheviny, a takzhe prodolzhitel'nost' sluzhby i otravlenie katalizatora. Vtoraya stadiya protsessa zaklyuchaetsya v osazhdenii oksalato'v toriya i urana (IV). Opisyvaetsya vliyanie shchavelevoj kisloty na otnoshenie torij/uran, temperatury i vremeni stareniya na otstaivanie i fil'tratsionnye kharakteristiki osadka i na keramicheskie svojstva poluchennykh poroshkov. Prokalka proizvodilas' kak v vosstanovitel'noj, tak i v okislitel'noj atmosferakh. Posle predvaritel'nykh ispytanij byli prinyaty dva standartnykh metoda izgotovleniya keramicheskikh izdelij, a imenno: kholodnaya pressovka i spekanie, ehkstruziya i spekanie. Spekaemost' razlichnykh poroshkov byla ispytana s pomoshch'yu ehtikh oboikh standartnykh metodov. S nekotorymi poroshkami byli polucheny plotnosti svyshe 95% teoreticheski dopustimoj. Uspeshno byli provedeny ispytaniya na vosproizvodimost'. (author)Original Title
Preparation d'un melange d'oxydes de thorium et d'uranium propre a la fabrication de combustible ceramique; Izgotovlenie keramicheskogo torievo-uranovogo okisla; Preparacion de mezclas de oxidos de uranio y torio, de tipo ceramico
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Source
International Atomic Energy Agency, Vienna (Austria); 582 p; Nov 1963; p. 37-53; Conference on New Nuclear Materials Technology, Including Non Metallic Fuel Elements; Prague (Czech Republic); 1-5 Jul 1963; ISSN 0074-1884; ; 17 figs., 2 tabs., 6 refs.
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ACTINIDE COMPOUNDS, ACTINIDES, ALUMINIUM COMPOUNDS, AMIDES, CARBONIC ACID DERIVATIVES, CHALCOGENIDES, DIMENSIONLESS NUMBERS, ELEMENTS, FABRICATION, HYDROGEN COMPOUNDS, INORGANIC ACIDS, INORGANIC COMPOUNDS, MATERIALS WORKING, METALS, NITRATES, NITROGEN COMPOUNDS, ORGANIC COMPOUNDS, ORGANIC NITROGEN COMPOUNDS, OXIDES, OXYGEN COMPOUNDS, PHYSICAL PROPERTIES, PLATINUM METALS, PRESSING, REACTOR COMPONENTS, THORIUM COMPOUNDS, TRANSITION ELEMENTS, URANIUM COMPOUNDS, URANYL COMPOUNDS
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AbstractAbstract
No abstract available
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Oct 1972; 7 p; 2. Italian-Polish meeting on some chemical, ceramic and metallurgic aspects of nuclear fuels; Rome, Italy; 3 Oct 1972
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Report
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Conference
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ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, HEAVY WATER MODERATED REACTORS, HWLWR TYPE REACTORS, MATERIALS WORKING, METALLURGY, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, THERMAL REACTORS, TIN ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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AbstractAbstract
No abstract available
Original Title
Le attivita del CNEN a Saluggia per la fabbricazione di combustibili nucleari
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Journal Article
Journal
Com. Naz. Energ. Nucl., Notiz; v. 17(8-9); p. 46-102
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Arcelli, G.; Bozzoni, T.; Coluccio, G.; Gatti, S.; Gerevini, T.; Testa, G.
International Atomic Energy Agency, Vienna (Austria)1977
International Atomic Energy Agency, Vienna (Austria)1977
AbstractAbstract
[en] This paper summarizes the main activities carried out in Italy from the last Geneva Conference (1971) in the field of LWR fuel design, manufacturing, testing and management. In fuel design, large effort has been devoted both to the assimilation of the information resulting from the licensing agreement with the US suppliers and to the development of an independent know-how through adequate R and D programs as well as to fuel behavior modeling activities. Among these it is worthwhile to mention the studies carried out by CNEN on the in-pile behavior of gadolinia fuel rods, the critical heat flux (CHF) and void fraction experiments, the overpower ramp tests on pre-irradiated fuel rods, the measurements of the pellet-cladding thermal conductance vs. burn-up and the investigation on fission gas release kinetics. The experience acquired with the fuel of the two LWR ENEL power stations, Garigliano BWR and Trino PWR, and some fuel management problems are reviewed. In this framework mention is made to the effort devoted to the acquisition of a wider knowledge on fuel behavior through post irradiation examination (PIE) of power reactor fuel elements as well as of experimental rods. The Italian fuel manufacturing capabilities are illustrated: they consist of the FN (Fabbricazioni Nucleari) plant at Bosco Marengo, owned by AGIP Nucleare and AMN, which has produced up-to-now a reload for Garigliano BWR and the first core for Caorso BWR and of COREN (COmbustibili REattori Nucleari) at Saluggia, owned by Breda, FIAT and Westinghouse, which has fabricated reloads for Trino PWR, including 8 UO2-PuO2 fuel bundles, while fuel loading for the Otto Hahn nuclear ship and fuel mechanical components for some PWRs have been fabricated by FIAT
[fr]
Cet article resume les principales activites menees en Italie depuis la derniere Conference de Geneve (1971) dans le domaine des etudes, de la fabrication, des essais et de la gestion du combustible LWR. En matiere de combustible, un grand effort a ete accompli, portant a la fois sur l'assimilation des informations, resultant de l'accord sur les licences de fabrication avec les fournisseurs des Etats-Unis, et au developpement d'une formulation independante d'instructions pratiques, grace a des programmes R et D appropries aussi bien qu'a des activites de recherche sur le comportement du combustible. Parmi ces dernieres, il convient de mentionner les etudes du CNEN sur le comportement en pile des combustibles de gadolinia en barres, sur le flux critique de chaleur (CHF), et les experiences du taux de permeabilite, les tests sur rampe de surpuissance sur barres de combustible pre-irradiees, les mesures de la conductance thermique gaine-combustible aux taux d'irradiation et l'enquete sur la cinetique de la detente des gaz de fission. L'experience acquise avec le combustible des deux centrales LWR de l'ENEL, Garigliano BWR et Trino PWR, et quelques problemes de gestion du combustible, sont egalement passes en revue. Dans ce cadre de travail, il est fait mention de l'effort consacre a l'acquisition d'une connaissance plus profonde du comportement du combustible, par examen post-irradiation (PIE) d'elements du combustible de reacteurs de puissance ainsi que de barres experimentales. On illustre les capacites de fabrication du combustible en Italie; ce sont les usines FN (Fabrications Nucleaires) de Bosco Marengo, propriete de l'AGIP Nucleaire, et AMN, qui a produit jusqu'a present une recharge pour le BWR de Garigliano et le premier noyau de reacteur pour Caorso BWR, ainsi que celle de COREN (Combustibili Reattori Nucleari) de Saluggia, propriete des recharges pour Trino PWR, comprenant 8 assemblages UO2-PuO2 de combustible, tandis que les charges de combustible pour le navire Otto Hahn et les composantes mecaniques du combustible pour certains PWR ont ete fabriquees par la FIATOriginal Title
Les progres Italiens dans l'etude, la fabrication, les essais et la gestion du combustible LWR
Primary Subject
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Source
1977; 10 p; International conference on nuclear power and its fuel cycles; Salzburg, Austria; 2 - 13 May 1977; 2.4.-.T.1./03.
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Arcelli, G.; Bozzoni, T.; Coluccio, G.; Gatti, S.; Gerevini, T.; Testa, G.
Nuclear power and its fuel cycle1977
Nuclear power and its fuel cycle1977
AbstractAbstract
[en] The paper summarizes the main activities carried out in Italy since the 1971 Geneva Conference in light-water reactor fuel design, manufacture, testing and management. In fuel design, much effort has been devoted both to the assimilation of information resulting from the licensing agreement with the United States, suppliers, and to the development of an independent know-how through adequate research and development programmes as well as to fuel behaviour modelling activities. Of these it is worth while mentioning the studies carried out by Comitatio Nazionale per l'Energia Nucleare (CNEN) on the in-pile behaviour of gadolinia fuel rods; the critical heat flux and void fraction experiments; the over-power ramp tests on pre-irradiated fuel rods; the measurements of the pellet-cladding thermal conductance versus burnup; and the investigation on fission-gas release kinetics. The experience acquired with the fuel of the two LWR ENEL power stations, Garigliano BWR and Trino PWR, and some fuel management problems, are reviewed. Mention is made of the effort devoted to acquiring a wider knowledge of fuel behaviour through the post-irradiation examination of power reactor fuel elements, and of experimental rods. Italian fuel manufacturing capabilities are illustrated - the FN (Fabbricazioni Nucleari) plant at Bosco Marengo, which has produced up-to-now a reload for Garigliano BWR and the first core for Caorso BWR; and COREN (Combustibili Reattori Nucleari) at Saluggia, which has fabricated reloads for Trino PWR, including eight UO2-PuO2 fuel bundles; while fuel loading for the Otto Hahn nuclear ship and fuel mechanical components for some PWRs have been made by Fiat. (author)
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Proceedings series; v. 2 p. 491-502; ISBN 92-0-050177-X; ; 1977; v. 2 p. 491-502; IAEA; Vienna; International conference on nuclear power and its fuel cycle; Salzburg, Austria; 2 - 13 May 1977; IAEA-CN--36/310
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