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Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires

Technical Report:

Abstract

This article begins with a review of the various materials which can be used and the cooling gases in which they may be heated, emphasis being placed on the importance of reaching temperatures as high as possible. This is followed by a few general remarks on the dry oxidation of metals and alloys, particularly with regard to diffusion phenomena and their various possible mechanisms, and also the methods of investigation employed. Finally, the behaviour of the chief nuclear materials heated in the various gases is studied successively. Materials used for fuel (metallic uranium, uranium oxide, carbides and silicides), canning materials (magnesium, aluminium, zirconium, beryllium, stainless and refractory steels), structural materials (ordinary or slightly alloyed steels), and finally moderators (graphite, beryllium oxide) are deal with in this way. This account is backed up both by the results obtained at the CEA and by work published outside or abroad up to the present day. In conclusion, every effort has been made to direct future research on the basis of the foregoing. Reprint of a paper published in Industries Atomiques - no. 9/10, 1959, p. 3-23 [French] Dans cet article, on passe tout d'abord en revue les divers materiaux utilisables et les gaz  More>>
Authors:
Darras, R. [1] 
  1. Commissariat a l'energie atomique et aux energies alternatives - CEA, Centre de Saclay, Section d'etude de la corrosion par gaz et metaux liquides (France)
Publication Date:
Jul 01, 1960
Product Type:
Technical Report
Report Number:
CEA-R-1481
Resource Relation:
Other Information: 54 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/
Subject:
36 MATERIALS SCIENCE; 37 INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; BERYLLIUM OXIDES; CARBON DIOXIDE; CHEMICAL REACTION KINETICS; COMBUSTION PROPERTIES; CORROSION; DIFFUSION; ELECTRIC CONDUCTIVITY; FORMATION FREE ENERGY; GRAPHITE; HUMIDITY; HYDRIDATION; MAGNOX; NITRIDATION; OXIDATION; STAINLESS STEELS; THORIUM OXIDES; URANIUM CARBIDES; URANIUM SILICIDES; ZIRCALOY
OSTI ID:
22682665
Research Organizations:
Commissariat a l'energie atomique et aux energies alternatives - CEA, Centre d'Etudes Nucleaires de Saclay, Service de Documentation, BP No.2, 91190 Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR1801448031317
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
25 page(s)
Announcement Date:
May 04, 2018

Technical Report:

Citation Formats

Darras, R. Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires. France: N. p., 1960. Web.
Darras, R. Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires. France.
Darras, R. 1960. "Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires." France.
@misc{etde_22682665,
title = {Corrosion by cooling gases in nuclear reactors; la corrosion par les gaz caloporteurs dans les reacteurs nucleaires}
author = {Darras, R.}
abstractNote = {This article begins with a review of the various materials which can be used and the cooling gases in which they may be heated, emphasis being placed on the importance of reaching temperatures as high as possible. This is followed by a few general remarks on the dry oxidation of metals and alloys, particularly with regard to diffusion phenomena and their various possible mechanisms, and also the methods of investigation employed. Finally, the behaviour of the chief nuclear materials heated in the various gases is studied successively. Materials used for fuel (metallic uranium, uranium oxide, carbides and silicides), canning materials (magnesium, aluminium, zirconium, beryllium, stainless and refractory steels), structural materials (ordinary or slightly alloyed steels), and finally moderators (graphite, beryllium oxide) are deal with in this way. This account is backed up both by the results obtained at the CEA and by work published outside or abroad up to the present day. In conclusion, every effort has been made to direct future research on the basis of the foregoing. Reprint of a paper published in Industries Atomiques - no. 9/10, 1959, p. 3-23 [French] Dans cet article, on passe tout d'abord en revue les divers materiaux utilisables et les gaz de refroidissement dans lesquels ils peuvent etre chauffes, en insistant sur l'interet d'atteindre des temperatures aussi elevees que possible. On rappelle ensuite quelques generalites sur l'oxydation seche des metaux et alliages, notamment en ce qui concerne les phenomenes de diffusion et leurs divers mecanismes possibles ainsi que les methodes d'etude. Enfin, le comportement des principaux materiaux nucleaires chauffes dans les divers gaz est etudie successivement. On traita ainsi des materiaux combustibles (uranium metallique, oxyde, carbures et siliciures d'uranium), des materiaux de gainage (magnesium, aluminium, zirconium, beryllium, aciers inoxydables et refractaires), des materiaux de structure (aciers ordinaires ou faiblement allies), et enfin des moderateurs (graphite, oxyde de beryllium). Au cours de l'expose, on s'appuie a la fois sur les resultats obtenus au CEA et sur les travaux exterieurs ou etrangers publies a ce jour. En conclusion, on s'efforce de degager une orientation pour les recherches ulterieures. Reproduction d'un article publie dans Industries Atomiques - no. 9/10, 1959, p. 3-23.}
place = {France}
year = {1960}
month = {Jul}
}