Embrittlement of reactor pressure vessels RPVs in pressurized water reactors PWRs

In this chapter, after giving an overview of the embrittlement of Western pressurized water reactor (PWR) reactor pressure vessel (RPV) beltline materials, together with the characteristics of PWR RPVs, such as their general specification, core region materials and the effects of variables on embrittlement, the surveillance database obtained from US, French and Japanese nuclear power plants (NPPs) and those from other countries is presented based on open literature. The surveillance program of each country is also briefiy described. Trends of surveillance data which will be obtained in the near future are described. The possibility of new data from reconstituted and miniature specimen techniques is described. 

2 Characteristics of pressurized water reactor (PWR) reactor pressure vessel (RPV) embrittlement 

This section provides a description of Western PWR RPVs which includes design features, applicable material specifications and differences among the various RPV components, and describes the characteristics of PWR RPV embrittlement. 

Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) 

Western-type PWR RPVs were designed by Westinghouse, Babcock Wilcox (B W) Company, Combustion Engineering (C-E), Inc., Framatome, Siemens/KWU, Doo San Heavy Industries and Mitsubishi Heavy Industries, Ltd (IAEA, 2009). 

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Embrittlement of reactor pressure vessels (RPVs) in pressurized water reactors (PWRs)... 

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