By D Féron, J-M Olive
Rigidity corrosion cracking is a huge challenge in gentle water nuclear reactors, even if pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear should be capable of are expecting the carrier lifetime of those energy crops and increase applicable upkeep and service practices to make sure secure long-term operation. this crucial e-book sums up key fresh learn on corrosion in gentle water reactors and its functional applications.
The publication is split into 4 components. It starts off with an summary of fabrics degradation because of tension corrosion, corrosion power tracking and passivation. half summarises study on susceptibility of fabrics to emphasize corrosion cracking and the methods it may be initiated. The 3rd a part of the ebook considers tension corrosion crack propagation procedures while the ultimate half comprises useful case stories of corrosion particularly vegetation. The booklet experiences corrosion in a number of fabrics akin to low alloy steels, stainless steels and nickel-based alloys.
With its unusual editor and staff of participants, Corrosion concerns in mild water reactors is a customary paintings for the nuclear industry.
- Summarises key contemporary examine on corrosion in mild water reactors
- Includes useful case studies
Read Online or Download Corrosion Issues in Light Water Reactors. Stress Corrosion Cracking PDF
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Extra resources for Corrosion Issues in Light Water Reactors. Stress Corrosion Cracking
On Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, TMS, 1999. 5. Molander, A. , Comparison of the corrosion potential for stainless steel measured in-plant and in laboratory during BWR normal water chemistry conditions, Proc 1998 Int. Conf. on Water Chemistry in Nuclear Power Plants, JAIF, (1998). 6. , Pein, K. and Ullberg, M. SKI Report 2004: 27, 2004. (in Swedish). 7. Molander, A. and Ullberg, M. The Corrosion Potential of Stainless Steel in BWR Environment – Comparison of Data and Modeling Results.
Staehle, J. A. Gorman, ‘Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in Pressurized Water Reactors: Parts 1, 2 and 3’, Corrosion, 59 (2003) 931–994, 60 (2004) 5–63, and 60 (2004) 115–180. L. E. Thomas, V. Y. Gertzman, S. M. Bruemmer, ‘Crack-tip microstructures and impurities in stress-corrosion-cracked Alloy 600 from recirculating and once-through steam generators’ Proceedings of 10th Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Lake Tahoe, NACE International (2001).
In spite of the cost of the measuring equipment, the measurements initially requested by the authorities were also shown to be economically attractive since such measurements permitted the hydrogen injection rate to be optimized. Electrochemical measurements have also been performed in PWR systems and mainly the feedwater system on the secondary side of PWRs. The measurements performed so far have shown that electrochemical measurements are very sensitive tools to detect and follow oxygen transients in the feedwater system.