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The Problem of Storing Fission Products Arising from the Processing of Irradiated Uranium-Molybdenum Alloys; Probleme du Stockage des Produits de Fission en Provenance du Traitement des Alliages Uranium-Molybdene Irradies; 041f 0420 041e 0411 041b 0415 041c 0410 0425 0420 0410 041d 0415 041d 0418 042f 041e 0422 0425 041e 0414 041e 0412 041f 041e 0421 041b 0415 041f 0415 0420 0415 0420 0410 0411 041e 0422 041a 0418 041e 0411 041b 0423 0427 0415 041d 041d 041e 0413 041e 0421 041f 041b 0410 0412 0410 0423 0420 0410 041d - 041c 041e 041b 0418 0411 0414 0415 041d ; El Problema del Almacenamiento de los Productos de Fision Procedentes del Tratamiento de las Aleaciones Uranio-Molibdeno Irradiadas

Conference:

Abstract

Uranium-molybdenum alloys are of value thanks to their in-pile behaviour but serious disadvantages arise in connection with the storing of fission products resulting from the processing of these alloys. Because of the insolubility of molybdenum it is impossible to concentrate a solution of fission products by evaporation, and for this reason we have directed our efforts towards the solubilization of molybdenum through the addition of reagents such as iron or phosphoric ions. In this way one can obtain final solutions of 60 g/l Mo with Fe 100 g/l Mo with PO{sub 4}H{sub 3}. The volumes to be stored are still considerable (especially with Fe) and the possibility of nitrate calcination in a fluidized bed was considered. The reaction takes place at about 400 Degree-Sign C. The behaviour of the ruthenium and the friability of the calcined solid (formation of considerable amounts of fine material) have led us to abandon this process in favour of the preparation of phosphate glasses. (author) [French] Les alliages U-Mo sont interessants par leur tenue en pile, mais ils presentent des inconvenients serieux quant au stockage des produits de fission resultant de leur traitement. L'insolubilite du molybdene interdit toute concentration par evaporation de la solution de  More>>
Authors:
Faugeras, P.; Kikindai, T. [1] 
  1. Commissariat a l'Energie Atomique, Paris (France)
Publication Date:
Feb 15, 1963
Product Type:
Conference
Resource Relation:
Conference: Symposium on Treatment and Storage of High-Level Radioactive Wastes Radioactive Wastes, Vienna (Austria), 8-12 Oct 1962; Other Information: 5 refs., 4 figs., 1 tab.; Related Information: In: Treatment and Storage of High-Level Radioactive Wastes. Proceedings of the Symposium on Treatment and Storage of High-Level Radioactive Wastes| 686 p.
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CALCINATION; EVAPORATION; FISSION PRODUCTS; FLUIDIZED BEDS; IRON; IRRADIATION; MOLYBDENUM; MOLYBDENUM ALLOYS; NITRATES; PHOSPHATE GLASS; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; REAGENTS; RUTHENIUM; URANIUM
OSTI ID:
22182112
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
French
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M3572006611
Submitting Site:
INIS
Size:
page(s) 119-131
Announcement Date:
Jan 23, 2014

Conference:

Citation Formats

Faugeras, P., and Kikindai, T. The Problem of Storing Fission Products Arising from the Processing of Irradiated Uranium-Molybdenum Alloys; Probleme du Stockage des Produits de Fission en Provenance du Traitement des Alliages Uranium-Molybdene Irradies; 041f 0420 041e 0411 041b 0415 041c 0410 0425 0420 0410 041d 0415 041d 0418 042f 041e 0422 0425 041e 0414 041e 0412 041f 041e 0421 041b 0415 041f 0415 0420 0415 0420 0410 0411 041e 0422 041a 0418 041e 0411 041b 0423 0427 0415 041d 041d 041e 0413 041e 0421 041f 041b 0410 0412 0410 0423 0420 0410 041d - 041c 041e 041b 0418 0411 0414 0415 041d ; El Problema del Almacenamiento de los Productos de Fision Procedentes del Tratamiento de las Aleaciones Uranio-Molibdeno Irradiadas. IAEA: N. p., 1963. Web.
Faugeras, P., & Kikindai, T. The Problem of Storing Fission Products Arising from the Processing of Irradiated Uranium-Molybdenum Alloys; Probleme du Stockage des Produits de Fission en Provenance du Traitement des Alliages Uranium-Molybdene Irradies; 041f 0420 041e 0411 041b 0415 041c 0410 0425 0420 0410 041d 0415 041d 0418 042f 041e 0422 0425 041e 0414 041e 0412 041f 041e 0421 041b 0415 041f 0415 0420 0415 0420 0410 0411 041e 0422 041a 0418 041e 0411 041b 0423 0427 0415 041d 041d 041e 0413 041e 0421 041f 041b 0410 0412 0410 0423 0420 0410 041d - 041c 041e 041b 0418 0411 0414 0415 041d ; El Problema del Almacenamiento de los Productos de Fision Procedentes del Tratamiento de las Aleaciones Uranio-Molibdeno Irradiadas. IAEA.
Faugeras, P., and Kikindai, T. 1963. "The Problem of Storing Fission Products Arising from the Processing of Irradiated Uranium-Molybdenum Alloys; Probleme du Stockage des Produits de Fission en Provenance du Traitement des Alliages Uranium-Molybdene Irradies; 041f 0420 041e 0411 041b 0415 041c 0410 0425 0420 0410 041d 0415 041d 0418 042f 041e 0422 0425 041e 0414 041e 0412 041f 041e 0421 041b 0415 041f 0415 0420 0415 0420 0410 0411 041e 0422 041a 0418 041e 0411 041b 0423 0427 0415 041d 041d 041e 0413 041e 0421 041f 041b 0410 0412 0410 0423 0420 0410 041d - 041c 041e 041b 0418 0411 0414 0415 041d ; El Problema del Almacenamiento de los Productos de Fision Procedentes del Tratamiento de las Aleaciones Uranio-Molibdeno Irradiadas." IAEA.
@misc{etde_22182112,
title = {The Problem of Storing Fission Products Arising from the Processing of Irradiated Uranium-Molybdenum Alloys; Probleme du Stockage des Produits de Fission en Provenance du Traitement des Alliages Uranium-Molybdene Irradies; 041f 0420 041e 0411 041b 0415 041c 0410 0425 0420 0410 041d 0415 041d 0418 042f 041e 0422 0425 041e 0414 041e 0412 041f 041e 0421 041b 0415 041f 0415 0420 0415 0420 0410 0411 041e 0422 041a 0418 041e 0411 041b 0423 0427 0415 041d 041d 041e 0413 041e 0421 041f 041b 0410 0412 0410 0423 0420 0410 041d - 041c 041e 041b 0418 0411 0414 0415 041d ; El Problema del Almacenamiento de los Productos de Fision Procedentes del Tratamiento de las Aleaciones Uranio-Molibdeno Irradiadas}
author = {Faugeras, P., and Kikindai, T.}
abstractNote = {Uranium-molybdenum alloys are of value thanks to their in-pile behaviour but serious disadvantages arise in connection with the storing of fission products resulting from the processing of these alloys. Because of the insolubility of molybdenum it is impossible to concentrate a solution of fission products by evaporation, and for this reason we have directed our efforts towards the solubilization of molybdenum through the addition of reagents such as iron or phosphoric ions. In this way one can obtain final solutions of 60 g/l Mo with Fe 100 g/l Mo with PO{sub 4}H{sub 3}. The volumes to be stored are still considerable (especially with Fe) and the possibility of nitrate calcination in a fluidized bed was considered. The reaction takes place at about 400 Degree-Sign C. The behaviour of the ruthenium and the friability of the calcined solid (formation of considerable amounts of fine material) have led us to abandon this process in favour of the preparation of phosphate glasses. (author) [French] Les alliages U-Mo sont interessants par leur tenue en pile, mais ils presentent des inconvenients serieux quant au stockage des produits de fission resultant de leur traitement. L'insolubilite du molybdene interdit toute concentration par evaporation de la solution de produits de fission. C'est pourquoi les auteurs ont oriente leurs etudes vers la solubilisation du molybdene par addition de reactifs tels que le fer ou les ions phosphoriques. Ainsi, on peut obtenir les solutions finales a 60 g/l Mo avec Fe, 100 g/l Mo avec PO{sub 4}H{sub 3} Les volumes a stocker sont encore importants (surtout avec Fe) et la calcination des nitrates dans un lit fluidise a ete etudiee. La reaction a lieu vers 400 Degree-Sign C. Le comportement du ruthenium et la friabilite du solide calcine (formation importante de fines) a conduit a abandonner ce procede au profit de la confection de verres phosphates. (author) [Spanish] Las aleaciones U-Mo son interesantes por la forma en que se comportan en el reactor, pero presentan serios inconvenientes en lo que respecta al almacenamiento de los productos de fision resultantes de su tratamiento. La insolubilidad del molibdeno impide concentrar por evaporacion las soluciones de los productos de fision. Por tal motivo, los autores han estudiado la posibilidad de solubilizar el molibdeno agregandole reactivos tales como el hierro o los iones fosforicos. De este modo, es posible obtener soluciones finales de 60 g/l Mo con hierro, 100 g/l Mo con PO{sub 4}H{sub 3}. Los volumenes que es preciso almacenar siguen siendo importantes (sobre todo con el hierro) y por eso se ha estudiado la calcinacion de los nitratos en un lecho fluidizado. La reaccion tiene lugar a los 400 Degree-Sign C aproximadamente. El comportamiento del rutenio y la friabilidad del solido calcinado (importante formacion de particulas menudas) ha inducido a los autores a reemplazar este procedimiento por el de preparacion de vidrios fosfAtados. (author) [Russian] Povedenie splavov uran-molibden v reaktore predstavljaet prakticheskij interes. Odnako voznikaet problema hranenija produktov delenija, kotorye poluchajutsja v rezul'tate ih pererabotki. V tom sluchae, kogda molibden nahoditsja v nerastvorennom sostojanii, ljuboe koncentrirovanie produktov delenija putem isparenija rastvora prakticheski nevozmozhno. Vot pochemu my orientirovalis' na izuchenie rastvorenija mo'libdena pribavleniem takih reagentov, kak zhelezo idi fosfat-iony. Mozhno poluchit' rastvor sostava: 60 g/l Mo s Re ili. 100 g/l Mo sPO{sub 4}H{sub 3} V jetom sluchae ob'edy, prednaznachennye dlja hranenija, uvelichivajutsja (osobenno pri dobavlenii Fe). Bylo izucheno prokalivanie nitratov v dvizhushhemsja sdoe. Reakcija prohodit pri temperature okolo 400 Degree-Sign C. Letuchest' rutenija i hrupkost' tverdogo prokalennogo veshhestva (vsledstvie obrazovanija znachitel'nogo kolichestva uglja) zastavila'nas otkazat'sja ot'jetogo processa i'perejti k izgotovleniju fosfatnyh stekol. (author)}
place = {IAEA}
year = {1963}
month = {Feb}
}