Investigation on Corrosion Behavior of High-Level Waste Container Materials

PRICM ◽  
2013 ◽  
pp. 167-179
Author(s):  
Qiufa Xu ◽  
Wei Wang ◽  
Xiaolu Pang ◽  
Quanlin Liu ◽  
Kewei Gao
Keyword(s):  
Corrosion Behavior ◽  
High Level Waste ◽  
Waste Container ◽  
High Level

The Use of Repassivation Potential in Predicting The Performance of High-Level Nuclear Waste Container Materials

1994 ◽  
Vol 353 ◽  
Author(s):  
Narasi Sridhar ◽  
Darrell Dunn ◽  
Gustavo Cragnolino
Keyword(s):  
Field Tests ◽  
Localized Corrosion ◽  
High Level Waste ◽  
Repassivation Potential ◽  
Waste Container ◽  
Highly Sensitive ◽  
Plant Equipment ◽  
Robust Parameter ◽  
High Level Nuclear Waste ◽  
High Level

AbstractLocalized corrosion in aqueous environments forms an important bounding condition for the performance assessment of high-level waste (HLW) container materials. A predictive methodology using repassivation potential is examined in this paper. It is shown, based on long-term (continuing for over 11 months) testing of alloy 825, that repassivation potential of deep pits or crevices is a conservative and robust parameter for the prediction of localized corrosion. In contrast, initiation potentials measured by short-term tests are non-conservative and highly sensitive to several surface and environmental factors. Corrosion data from various field tests and plant equipment performance are analyzed in terms of the applicability of repassivation potential. The applicability of repassivation potential for predicting the occurrence of stress corrosion cracking (SCC) and intergranular corrosion in chloride containing environments is also examined.

Corrosion behavior of Alloy 690 and Alloy 693 in simulated nuclear high level waste medium

2011 ◽  
Vol 418 (1-3) ◽  
pp. 27-37 ◽  
Author(s):  
Pradeep Kumar Samantaroy ◽  
Girija Suresh ◽  
Ranita Paul ◽  
U. Kamachi Mudali ◽  
Baldev Raj
Keyword(s):  
Corrosion Behavior ◽  
High Level Waste ◽  
Alloy 690 ◽  
High Level

An Approach to Analysis of High Level waste Container Performance in an Unsaturated Repository Environment

1993 ◽  
Vol 333 ◽  
Author(s):  
John C. Walton ◽  
Narasi Sridhar ◽  
Gustavo Cragnolino ◽  
Tony Torng ◽  
Prasad Nair
Keyword(s):  
Dominant Role ◽  
Near Field ◽  
Temperature Fields ◽  
Localized Corrosion ◽  
High Level Waste ◽  
Quantitative Methodology ◽  
Waste Container ◽  
Wide Range ◽  
Engineered Barrier ◽  
High Level

ABSTRACTOne of the requirements for the performance of waste packages prescribed in 10CFR 60.113 is that the high level waste must be “substantially completely” contained for a minimum period of 300 to 1000 years. During this period, the radiation and thermal conditions in the engineered barrier system and the near-field environment are dominated by fission product decay. In the present U.S design of the engineered barrier system, the outer container plays a dominant role in maintaining radionuclide containment. A quantitative methodology for analyzing the performance of the container is described in this paper. This methodology enables prediction of the evolution of the waste package environment in terms of temperature fields, stability of liquid water on the container surface, and concentration of aggressive ions such as chloride. The initiation and propagation of localized corrosion is determined by the corrosion potential of the container material and critical potentials for localized corrosion. The coiTOsion potential is estimated from the kinetics of the anodic and cathodic reactions including oxygen diffusion through scale layers formed on the container surface. The methodology described is applicable to a wide range of metals, alloys and environmental conditions.

Corrosion Behavior of Alloy 600 in Simulated Nuclear High Level Waste Medium

2012 ◽  
Vol 22 (4) ◽  
pp. 1041-1053 ◽  
Author(s):  
Pradeep Kumar Samantaroy ◽  
Girija Suresh ◽  
Nanda Gopala Krishna ◽  
U. Kamachi Mudali
Keyword(s):  
Corrosion Behavior ◽  
High Level Waste ◽  
Alloy 600 ◽  
High Level
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