A Review on Noble Metals in Controlling Intergranular Stress Corrosion Cracking in BWRs

Author:

K. Bharath1,Devendra 2,Praveen B. M.3

Affiliation:

1. Dept of Chemistry, Srinivas University, College of Engineering and Technology, Mukka,

2. Dept of Chemistry, Srinivas University, College of Engineering and Technology, Mukka

3. Dept of Chemistry,Srinivas University, College of Engineering and Technology, Mukka

Abstract

Intergranular stress corrosion cracking (IGSCC) is common in boiling water reactor (BWR) components. Corrosion problem is a serious matter that has overwhelmed the light water reactor (LWR) industry for many years. The conditions in which IGSCC takes pace due to stress, a sharpen microstructure and an environment that will facilitate the cracking while injecting H2 into the feed water system. Nuclear reactor made up of stainless steel facing serious Intergranular stress corrosion cracking due to the injection of hydrogen dosage into the nuclear reactor in the form of heavy water chemistry. Moderately large concentrations of H2 may be essential in nuclear power plants to bring the ECP below the critical value of –230 mV (SHE) to ease Intergranular stress corrosion cracking, which in turn results in an increase of steam line dose rate and shutdown dose rate and hence heavy water chemistry is limited in the nuclear reactor plant. Hence this led to the development of the concept called noble metal chemical addition (NMCA) to control IGSCC even in the presence of H2. This review gives the insights and development of NMCA on corrosion control in BWRs.

Publisher

Srinivas University

Subject

General Medicine

Reference18 articles.

1. https://en.wikipedia.org/wiki/Boiling_water_reactor referred on 25/12/2018.

2. https://www.euronuclear.org/info/encyclopedia/n/nuclear-power-plant-world-wide.htm referred on 28/12/2018.

3. Hettiarachchi S. A. Review of BWR Fuel Performance under Modern Water Chemistry Conditions,7-9. Retrieved from https://pdfs.semanticscholar.org/ 15f1/cb5ffddae79fa1d99a14c8146cf63a4f3e96.pdf.

4. Andresen P. L. (2008). Emerging issues and fundamental processes in environmental cracking in hot water Corrosion. Advances in Environmentally Assisted Cracking, 64, 439–464. DOI: 10.5006/1.3278483.

5. Garud.Y. S, (2015). Significance and Assessment of Low Temperature Creep and Irradiation Creep in Nuclear Reactor Application. Procedia Engineering, 130, 1162-1176. DOI:10.1016/j.proeng.2015.12.284.

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