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Recent developments in the field of refractory fuels; Developpements recents dans le domaine des combustibles refractaires

Abstract

The main part of the work carried out in the field of ceramic fuels by the Commissariat a l'Energie Atomique during recent years, has been in the direction of uranium dioxide and the uranium-carbon alloys. Uranium dioxide is being studied with the aim of using it as a fuel in the first core of EL-4, in which an integrated thermal conductivity of 29 W/cm is expected at the hottest point for a surface temperature of about 750 C. We concentrated on developing a process for preparing a dioxide powder of suitable characteristics and for sintering this powder, and on evaluating the main properties of the material obtained in the light of the conditions under which they will be used - micro-structural aspect and pore distribution, - mechanical and thermal behaviour in cylindrical form, - control of excess oxygen in the industrial products, - behaviour of the gaseous fission products at high temperatures after or during the course of irradiation. Our aim in the case of uranium carbides has been to determine the conditions of industrial manufacturing of a suitable fuel with a composition close to This has led us to undertake a number of fundamental investigations into - the domain  More>>
Authors:
Accary, A; Delmas, R [1] 
  1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1964
Product Type:
Technical Report
Report Number:
CEA-R-2674
Resource Relation:
Other Information: 35 refs
Subject:
36 MATERIALS SCIENCE; MICROSTRUCTURE; NITROGEN; NUCLEAR FUELS; OXYGEN; POROSITY; REFRACTORY METALS; SINTERED MATERIALS; URANIUM CARBIDES; URANIUM DIOXIDE
OSTI ID:
20668368
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR05R2674107069
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
22 pages
Announcement Date:
Dec 19, 2005

Citation Formats

Accary, A, and Delmas, R. Recent developments in the field of refractory fuels; Developpements recents dans le domaine des combustibles refractaires. France: N. p., 1964. Web.
Accary, A, & Delmas, R. Recent developments in the field of refractory fuels; Developpements recents dans le domaine des combustibles refractaires. France.
Accary, A, and Delmas, R. 1964. "Recent developments in the field of refractory fuels; Developpements recents dans le domaine des combustibles refractaires." France.
@misc{etde_20668368,
title = {Recent developments in the field of refractory fuels; Developpements recents dans le domaine des combustibles refractaires}
author = {Accary, A, and Delmas, R}
abstractNote = {The main part of the work carried out in the field of ceramic fuels by the Commissariat a l'Energie Atomique during recent years, has been in the direction of uranium dioxide and the uranium-carbon alloys. Uranium dioxide is being studied with the aim of using it as a fuel in the first core of EL-4, in which an integrated thermal conductivity of 29 W/cm is expected at the hottest point for a surface temperature of about 750 C. We concentrated on developing a process for preparing a dioxide powder of suitable characteristics and for sintering this powder, and on evaluating the main properties of the material obtained in the light of the conditions under which they will be used - micro-structural aspect and pore distribution, - mechanical and thermal behaviour in cylindrical form, - control of excess oxygen in the industrial products, - behaviour of the gaseous fission products at high temperatures after or during the course of irradiation. Our aim in the case of uranium carbides has been to determine the conditions of industrial manufacturing of a suitable fuel with a composition close to This has led us to undertake a number of fundamental investigations into - the domain of existence of non-stoichiometric UC, - the influence of elements of O and N on the properties of the UC in which they are dissolved, - the compatibility of uranium-carbon alloys with the different metallic or ceramic materials used for the sheath, - the corrosion of uranium-carbon alloys by H{sub 2}O and CO{sub 2}, - methods of preparing high purity samples, - in-pile irradiation devices for the investigation of these materials in the region of possible operating temperatures. In parallel with these fundamental investigations, we have attempted to define a procedure for the fabrication of uranium-carbon alloys of composition very close to UC which would, in its industrial application, lead to better results than the existent methods from the technical or economical points of view (i.e. sintering or arc fusion). This latter method is based on fusion by electronic bombardment associated with the continuous casting. (authors) [French] L'effort des recentes annees au Commissariat a l'Energie Atomique dans le domaine des combustibles ceramiques a surtout porte sur le bi-oxyde d'uranium et les alliages uranium-carbone. Le bi-oxyde d'uranium est etudie dans l'optique de son utilisation comme combustible de la premiere charge d'EL 4, dans laquelle on impose au point le plus charge une conductibilite thermique integree de 29 W/cm pour une temperature de surface de 750 C environ. On s'est specialement preoccupe de mettre en place un procede de preparation d'une poudre de bi-oxyde de bonnes caracteristiques et le frittage industriel de cette poudre, et d'evaluer les principales proprietes des corps obtenus en relation avec les conditions des corps obtenus en relation avec les conditions prevues de leur utilisation: - aspect de micro-structure et distribution des pores, - comportement mecanique et thermique en geometrie cylindrique, - controle de l'oxygene excedentaire dans les produits industriels, - compatibilite aux hautes temperatures avec les oxydes utilisables comme isolants thermiques, - comportement des produits de fission gazeux a haute temperature apres irradiation ou au cours de l'irradiation. Dans le cas des carbures d'uranium, notre but a ete de determiner les conditions de fabrication industrielle d'un combustible satisfaisant de composition voisine de UC. Ceci nous a conduits a entreprendre un certain nombre d'etudes fondamentales Sur le domaine d'existence de UC non stoechiometrique, - l'influence, sur les proprietes de UC, des elements O et N dissous dans ce materiau, - la compatibilite des alliages uranium-carbone avec differents materiaux de gaine metalliques ou ceramiques, - la corrosion des alliages uranium-carbone par H{sub 2}O et CO{sub 2}, - les methodes de preparation d'echantillons de haute purete, - les dispositifs d'irradiation en pile permettant l'etude de ces materiaux dans le domaine des temperatures possibles d'utilisation. Parallelement a ces etudes fondamentales, nous nous sommes attaches a definir une methode de fabrication d'alliages uranium-carbone de composition tres voisine de UC qui conduise, dans son application industrielle, a des resultats meilleurs au point de vue technique ou au point de vue economique que les methodes existantes (a savoir le frittage ou la fusion a l'arc). Cette methode met en oeuvre la fusion par bombardement electronique associe a la coulee continue. - la compatibilite des alliages uranium-carbone avec differents materiaux de gaine metalliques ou ceramiques, - la corrosion des alliages uranium-carbone par H{sub 2}O et CO{sub 2}, - les methodes de preparation d'echantillons de haute purete, - les dispositifs d'irradiation en pile permettant l'etude de ces materiaux dans le domaine des temperatures possibles d'utilisation. Parallelement a ces etudes fondamentales, nous nous sommes attaches a definir une methode de fabrication d'alliages uranium-carbone de composition tres voisine de UC qui conduise, dans son application industrielle, a des resultats meilleurs au point de vue technique ou au point de vue economique que les methodes existantes (a savoir le frittage ou la fusion a l'arc). Cette methode met en oeuvre la fusion par bombardement electronique associe a la coulee continue. (auteurs)}
place = {France}
year = {1964}
month = {Jul}
}