Hydrogen water chemistry for BWRs

Bilanin, W.J.; Cubicciotti, Daniel; Jones, Robin L.; Machiels, Albert J.; Nelson, L.; Wood, C.J.

doi:10.1016/0149-1970(87)90011-4

Cited by 10 publications

(2 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Corrosion fatigue crack was generally observed to propagate at rates much faster than SCC. As a mitigative measure taken by the nuclear industry, the injection of hydrogen into the plant coolant had been used to suppress the growth of SCC cracks in stainless steel components in recent years [18].…”

Section: Introductionmentioning

confidence: 99%

Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

Chiang

Young

Huang

2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: Introductionmentioning

confidence: 99%

Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

Chiang

Young

Huang

2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…The effect of DH in cooling water has been investigated in past score. Hydrogen has been proved being able to harvest corrodants such as dissolved oxygen and hydrogen peroxides 11) and consequently retarding crack growth rate (CGR). 12,13) In pressurized water reactors, hydrogen is also responsible for controlling pH value.…”

Section: Introductionmentioning

confidence: 99%

Stress Corrosion Cracking Behavior of Type 316L and Type 310S Stainless Steels in Fusion Relevant Environments

Huang

Kimura

2018

Mater. Trans.

View full text Add to dashboard Cite

Stress corrosion cracking (SCC) susceptibility of type 316L and type 310S SS in pressurized water (561/613 K) and supercritical water (773 K) at deaerated condition and with dissolved-hydrogen (DH) ranging from 0.014 to 1.4 ppm were examined by means of slow strain rate test (SSRT) method at a strain rate of 5 © 10 ¹7 s ¹1. SCC susceptibility of type 316L SS depends on test temperature and DH content. The SCC susceptibility, which was evaluated as a brittle fracture ratio, increased with increasing test temperature from 561 to 613 K, while it became much smaller in supercritical water at 773 K. At 613 K, the fracture ratio of intergranular (IG) SCC increased with increasing DH content in the pressurized water, although almost no IGSCC was observed at 561 K at any DH conditions. However, the IGSCC initiated at near specimen surface and transferred to transgranular (TG) SCC inside the specimen. The SCC susceptibility of type 310S SS is significantly lower than that of type 316L SS in the hydrogenated water at 561 and 613 K, while the trend appears to be reverse at 773 K. It is suggested that higher DH content in water is necessary to trigger IGSCC than TGSCC at 613 K.

show abstract

Equilibrium chemistry of nitrogen and potential-pH diagrams for the Fe-Cr-H2O system in bwr water

Cubicciotti

1989

Journal of Nuclear Materials

View full text Add to dashboard Cite

Hydrogen water chemistry for BWRs

Cited by 10 publications

References 4 publications

Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

Stress Corrosion Cracking Behavior of Type 316L and Type 310S Stainless Steels in Fusion Relevant Environments

Equilibrium chemistry of nitrogen and potential-pH diagrams for the Fe-Cr-H2O system in bwr water

Contact Info

Product

Resources

About