<departmental bulletin paper>
In-situ observation of damage formation in Fe-Mn alloy

Creator
Language
Publisher
Date
Source Title
Vol
First Page
Last Page
Publication Type
Access Rights
JaLC DOI
Abstract PWR type nuclear reactor pressure vessels is added stress when it during operation. Therefore it is important to know the effect of irradiation brittleness of the material. To study the influence of t...he stress on the nuclear reactor pressure vessel steal, the sample was irradiated under applied stress by using a high voltage electron microscope. Fe-1.4(w %) Mn alloy was used in this study as model alloy of A533B steel. The influence of the damage formation process was discussed in this paper.show more

Hide fulltext details.

pdf 139_p141 pdf 10.6 MB 294  

Details

PISSN
NCID
Record ID
Peer-Reviewed
Subject Terms
Type
Created Date 2013.08.24
Modified Date 2023.02.27

People who viewed this item also viewed