The release of corrosion products by the various components of the primary system into the cooling water may induce some issues on reactor control and on radiation dose rates. Several ways are available to reduce the amount and transportation of corrosion products in the primary coolant. The first approach is related to the materials used in the primary system. The paper presents the recent feedback regarding the primary coolant chemistry and radiochemistry after Steam Generators Replacements (SGR). The second approach is to optimize the primary water chemistry to reduce the release and the transport of the corrosion products through pH control by LiOH concentration. However, a detrimental effect of increased lithium hydroxide concentration on time to failure of irradiated SS 304 was clearly shown. Considering this risk, EDF is not favourable to the implementation of any elevated lithium chemistry program for its reactors without a better knowledge of the lithium hydroxide influence on IASCC of stainless steels.
|Title of host publication||Nuclear Plant Chemistry Conference 2010 (NPC 2010) |
|Subtitle of host publication||International Conference on Water Chemistry of Nuclear Reactor Systems and 8th International Radiolysis, Electrochemistry and Materials Performance Workshop : Quebec City, Quebec, Canada, 3-7 October 2010|
|Place of Publication||Toronto|
|Number of pages||18|
|Publication status||Published - 2010|
|MoE publication type||A4 Article in a conference publication|
- stainless steel