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Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques

Abstract

In order to study the effect of an external pressure on the limitation of swelling due to fission-gas precipitation, some irradiations have been carried out at burn-ups of about 35.000 MWd/ton, and at average sample temperatures of 575 Celsius degrees, of non-alloyed uranium and uranium 8 per cent molybdenum gained in a thick stainless steel can. A cylindrical central hole allows a fuel swelling from 20 to 33 per cent according to the experiment. After irradiation, the uranium samples showed two types of can rupture: one is due to the fuel swelling, and the other, to the pressure of the fission gases, released through a network of microcracks. The cans of the uranium-molybdenum samples are all undamaged and it is shown that the gas release occurs by interconnection of the bubbles for swelling values higher than those obtained in the case of uranium. For each type of fuel, a swelling-fission gas release relationship is established. The results suggest that good performances with a metallic fuel intended for use in fast reactor conditions can be obtained. (author) [French] Afin d'etudier l'effet d'une pression exterieure sur la limitation du gonflement due a la precipitation des gaz de fission, on a irradie a  More>>
Authors:
Kryger, B [1] 
  1. Commissariat a l'Energie Atomique, Fontenay-aux-Roses (France). Centre d'Etudes Nucleaires
Publication Date:
Oct 01, 1969
Product Type:
Thesis/Dissertation
Report Number:
CEA-R-3888
Resource Relation:
Other Information: TH: These; 30 refs; PBD: Oct 1969
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; BURNUP; FISSION PRODUCT RELEASE; FRACTURES; FUEL ELEMENT FAILURE; FUEL INTEGRITY; FUEL-CLADDING INTERACTIONS; PHYSICAL RADIATION EFFECTS; STAINLESS STEELS; SWELLING; URANIUM; URANIUM-MOLYBDENUM FUELS
OSTI ID:
20552721
Research Organizations:
CEA Fontenay-aux-Roses, 92 (France); Conservatoire National des Arts et Metiers (CNAM), 75 - Paris (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR04R3888007978
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
91 pages
Announcement Date:

Citation Formats

Kryger, B. Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques. France: N. p., 1969. Web.
Kryger, B. Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques. France.
Kryger, B. 1969. "Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques." France.
@misc{etde_20552721,
title = {Contribution to the study of the fission-gas release in metallic nuclear fuels; Contribution a l'etude du degagement des gaz de fission dans les combustibles nucleaires metalliques}
author = {Kryger, B}
abstractNote = {In order to study the effect of an external pressure on the limitation of swelling due to fission-gas precipitation, some irradiations have been carried out at burn-ups of about 35.000 MWd/ton, and at average sample temperatures of 575 Celsius degrees, of non-alloyed uranium and uranium 8 per cent molybdenum gained in a thick stainless steel can. A cylindrical central hole allows a fuel swelling from 20 to 33 per cent according to the experiment. After irradiation, the uranium samples showed two types of can rupture: one is due to the fuel swelling, and the other, to the pressure of the fission gases, released through a network of microcracks. The cans of the uranium-molybdenum samples are all undamaged and it is shown that the gas release occurs by interconnection of the bubbles for swelling values higher than those obtained in the case of uranium. For each type of fuel, a swelling-fission gas release relationship is established. The results suggest that good performances with a metallic fuel intended for use in fast reactor conditions can be obtained. (author) [French] Afin d'etudier l'effet d'une pression exterieure sur la limitation du gonflement due a la precipitation des gaz de fission, on a irradie a des taux de combustion d'environ 35.000 MWj/t et a des temperatures moyennes de 575 degres des echantillons d'uranium non allie et d'uranium-molybdene 8 pour cent contenus dans une gaine en acier inoxydable epaisse. Un trou cylindrique central permet au combustible de gonfler librement de 20 a 33 pour cent suivant les cas. Apres irradiation les echantillons d'uranium presentent deux types de ruptures de gaine: l'une due au gonflement du combustible, l'autre a la pression des gaz degages, ce degagement des gaz etant provoque par un reseau de micro-fissures. Les gaines des echantillons d'alliage uranium-molybdene sont toutes intactes et l'on montre que le relachement des gaz opere par interconnexion des bulles pour des valeurs de gonflement plus elevees que dans le cas de l'uranium. On etablit pour chaque type de combustible une relation gonflement-degagement des gaz de fission. Les resultats suggerent la possibilite d'obtenir des performances elevees avec un combustible metallique destine a fonctionner dans les conditions d'un reacteur rapide. (auteur)}
place = {France}
year = {1969}
month = {Oct}
}