Skip to content
RDL
Network
Ecosystem
Switch app
TR
About
FAQ
Sign in
Get started
The electrochemical properties of alloy 690 in simulated pressurized water reactor primary water: Effect of temperature — Jie Yang (2019) | RDL Network
Back
Cite
Save
Save for later
Share
Home
Publications
The electrochemical properties of alloy 690 in simulated pressurized water reactor primary water: Effect of temperature
Shared by
Digby D Macdonald
University of California, Berkeley
The electrochemical properties of alloy 690 in simulated pressurized water reactor primary water: Effect of temperature
Article
2019
en
Authors
+2 more
JY
Jie Yang
YL
Yanhui Li
AX
Aoni Xu
Discussion
(0)
Sign in
to like and join the discussion.
No comments yet. Be the first to comment.
Related publications
Article
2019
Effects of temperature and pH on the electrochemical behaviour of alloy 600 in simulated pressurized water reactor primary water
Jie Yang
,
Yanhui Li
,
Digby D Macdonald
Article
2006
Electrochemical Impedance Study of Zirconium under Simulated Boiling Water Reactor Operating Conditions
Jiahe Ai
,
Yingzi Chen
,
Mirna Urquidi Macdonald
,
Digby D Macdonald
Article
1996
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits — III: Effect of Reactor Power Level
Tsung‐Kuang Yeh
,
Digby D Macdonald
Article
2005
Main Features of the Core Melt Stabilization System of the European Pressurized Water Reactor (EPR)
D. Bittermann
,
Manfred M. Fischer
,
Markus Nie
Article
1980
Measurement of pH in Simulated Water-Cooled Nuclear Reactor Heat Transport Circuits
Digby D Macdonald
,
Paul R. Wentrcek
,
Arthur C. Scott
.webp){kind=small}
Discussion(0)
No comments yet. Be the first to comment.