BARC/PUB/2016/1368

 
 

Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steel

 
     
 
Author(s)

Roychowdhury, S.; Seifert, H. P.; Spatig, P.; and others
(MP&CED)

Source

Journal of Nuclear Materials, 2016. Vol. 478: pp. 343-364

ABSTRACT

Structural integrity of reactor pressure vessels (RPV) is critical for safety and lifetime. Possible degradation of fracture resistance of RPV steel due to exposure to coolant and hydrogen is a concern. In this study tensile and elastic-plastic fracture mechanics (EPFM) tests in air (hydrogen pre-charged) and EFPM tests in hydrogenated/oxygenated high-temperature water (HTW) was done, using a low-alloy RPV steel. 2e5 wppm hydrogen caused embrittlement in air tensile tests at room temperature (25 °C) and at 288 °C, effects being more significant at 25 °C and in simulated weld coarse grain heat affected zone material. Embrittlement at 288 °C is strain rate dependent and is due to localized plastic deformation. Hydrogen pre-charging/HTWexposure did not deteriorate the fracture resistance at 288 °C in base metal, for investigated loading rate range. Clear change in fracture morphology and deformation structures was observed, similar to that after air tests with hydrogen.

 
 
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