Affordable Access

Publisher Website

Irradiation dans le reacteur el 3 de tubes en uranium faiblement allie

Authors
Journal
Journal of Nuclear Materials
0022-3115
Publisher
Elsevier
Publication Date
Volume
31
Issue
2
Identifiers
DOI: 10.1016/0022-3115(69)90190-1

Abstract

Abstract Fuel elements have been made by industrial methods from 2 uranium alloys containing Al, Fe, Si, Cr (Sicral F1 and Sicral F2) and from 3 uranium alloys containing Cr, Mo, Fe and Si (U-Cr 0,1%; U-Mo-Cr-Fe and U-Si-Cr) in various proportions. Information is presented about the structure mechanical strength creep resistance and pre-irradiation thermal conductivity of these fuel elements. The five alloys were each irradiated to two different neutron doses in the range 1300–4200 MWd tonne . The irradiation temperature was 250 °C at the tube surface and reached a maximum of 630 °C at the internal interface. During irradiation, the thermal conductivity of one of the alloys decreased by 35% at a dose of 5000 MWd/tonne; the density also decreased and we noted the appearance of a porous ring at temperatures slightly below 500°C. Substantial differences in the change of density consequence on irradiation were found between the five alloys, “Sicral f 1” being particularly good, uranium-chromium particularly bad. The possible explanations for these differences are discussed: mechanical strength and creep resistance do not have an important role in this connection.

There are no comments yet on this publication. Be the first to share your thoughts.

Statistics

Seen <100 times
0 Comments

More articles like this

Conservation de germes de phase α en phase β dans...

on Journal of Nuclear Materials Jan 01, 1961

Contribution a l'etude du durcissement par irradia...

on Journal of Nuclear Materials Jan 01, 1966

Corrosion des aciers faiblement allies dans le gaz...

on Journal of Nuclear Materials Jan 01, 1968

Combustible pour réacteurs de recherche. Le dévelo...

on Revue Générale Nucléaire Nov 01, 1985
More articles like this..