Menu
Search
Filters
Close
Menu

08608 Modeling the Effects of Nuclear Environments on Crevice Corrosion of Pure Nickel by Coupling of Phase and Polarization Behavior

Picture for 08608 Modeling the Effects of Nuclear Environments on Crevice Corrosion of Pure Nickel by Coupling o
Available for download
Product Number: 51300-08608-SG
ISBN: 08608 2008 CP
Author: Hans Hoffmeister
Publication Date: 2008
$0.00
$20.00
$20.00
As from frequent observations Stress Corrosion Cracking (SCC) of nuclear reactor components may be initiated and its propagation also controlled by local pitting and crevice corrosion. Deterministic modeling of local corrosion including incubation times for crevice corrosion and related anodic acidification should therefore provide a basis for component lifetime predictions. Based on previous work for room temperature (RT), the crevice corrosion at 288°C of nickel as an important base element in respective high alloyed nuclear materials is modeled by coupling anodic polarization with formation of nickel oxide and chloride calculated from the water-hydrogen-nickelchloride heterogeneous phase equilibrium diagram. As a boundary condition, hydrogen treatment of irradiation subjected cooling water for reduction of corrosion potentials and mitigation of SCC in Boiling Water Reactors (BWR) is included.
As from frequent observations Stress Corrosion Cracking (SCC) of nuclear reactor components may be initiated and its propagation also controlled by local pitting and crevice corrosion. Deterministic modeling of local corrosion including incubation times for crevice corrosion and related anodic acidification should therefore provide a basis for component lifetime predictions. Based on previous work for room temperature (RT), the crevice corrosion at 288°C of nickel as an important base element in respective high alloyed nuclear materials is modeled by coupling anodic polarization with formation of nickel oxide and chloride calculated from the water-hydrogen-nickelchloride heterogeneous phase equilibrium diagram. As a boundary condition, hydrogen treatment of irradiation subjected cooling water for reduction of corrosion potentials and mitigation of SCC in Boiling Water Reactors (BWR) is included.
Product tags
Also Purchased
Picture for 08602 Effect of H2 on SCC Growth Rates of Nickel Alloys
Available for download

08602 Effect of H2 on SCC Growth Rates of Nickel Alloys

Product Number: 51300-08602-SG
ISBN: 08602 2008 CP
Author: Peter L. Andresen
Publication Date: 2008
$20.00
Picture for 08599 Stress Corrosion Cracking of Carbon Steel in Nitrate and Carbonate Wastes at Hanford
Available for download

08599 Stress Corrosion Cracking of Carbon Steel in Nitrate and Carbonate Wastes at Hanford

Product Number: 51300-08599-SG
ISBN: 08599 2008 CP
Author: C. Brossia, C. Scott, J. Beavers, G. Edgemon, G. Frankel, H. Berman, and K. Boomer
Publication Date: 2008
$20.00
Picture for 08604 Statistical Analysis on Stress Corrosion Cracking of Type 316L and Type 316 Stainless Steels i
Available for download

08604 Statistical Analysis on Stress Corrosion Cracking of Type 316L and Type 316 Stainless Steels in High Temperature Water

Product Number: 51300-08604-SG
ISBN: 08604 2008 CP
Author: Masami Mayuzumi, Nobuhisa Ishiyama, Kentaro Oonaka, Yoshihiro Mizutani, and Jun-ichi Tani
Publication Date: 2008
$20.00
Categories
Industry
Recently viewed
Popular tags
View all

Association for Materials Protection and Performance

© AMPP All Rights Reserved.
Membership Terms of Content Use
Contact Customer Support