Compatibility of Structural Materials with Sodium According to Data from the Experience Gained in 40 Years of Operation of the BR-5/BR-10 Reactor

The results of investigations of the corrosion characteristics of samples of structural materials cut from the main sodium loops of a BR-5/BR-10 sodium-cooled research reactor during operation over the period 1959-1999 are presented. Analysis of the results of the materials-engineering investigation...

Full description

Saved in:
Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2001-11, Vol.91 (5), p.951-955
Main Authors: Karpov, A V, Kononyuk, M Kh, Mamaev, L I, Kulikov, Yu L
Format: Article
Language:English
Subjects:
Atomic energy
Coolants
Corrosion
Corrosion rate
Nuclear power generation
Nuclear reactors
Reactors
Sodium
Structural materials
Studies
Citations: Items that cite this one
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:The results of investigations of the corrosion characteristics of samples of structural materials cut from the main sodium loops of a BR-5/BR-10 sodium-cooled research reactor during operation over the period 1959-1999 are presented. Analysis of the results of the materials-engineering investigations show that the sodium coolant has good corrosion characteristics and that the operating lifetime of sodium equipment in commercial fast reactors can be increased to 60 yr and longer.[PUBLICATION ABSTRACT]
ISSN:1063-4258
1573-8205
DOI:10.1023/A:1014274009267