Abstract
In order to mitigate PWSCC initiation and propagation in Ni base alloys, Japanese PWR utilities desire to employ optimized dissolved hydrogen (DH) control operation in the near future. Prior to the application of the optimized DH control operation to PWR, the effect of DH concentration on the fuel crud deposition should be clarified.
Crud deposition tests were carried out in boric acid (1200ppm) + lithium hydroxide (2.2ppm) + hydrogen (7 to 25cm3-STP/kg-H2O) solutions at 325°C under sub-cooled boiling and non-irradiated conditions. The corrosion resistance of zircaloy-4 was also investigated.
From the test results, it was revealed that a crud layer composed of NiFe2O4 and NiO was formed on zircaloy-4 fuel cladding. NiO was easy to form in the crud layer under the 7cm3-STP/kg-H2O condition. The amounts of deposited crud layer, boron incorporated into the crud layer and the corrosion resistance of the zircaloy-4 cladding were not affected by DH concentration.
This is a preview of subscription content, log in via an institution to check access.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Preview
Unable to display preview. Download preview PDF.
References
“NRC Information Notice Effects of CRUD Buildup and Boron Deposition on Power Distribution and Shutdown Margin”, NRC Information Notice Vol.97–85, (1997).
C. Cheng, P. Frattini, B. Armstrong, J. Bosma, K. Epperson, P. Kennamore, T. Moser, K. Sheppard, and A. Strasser, “PWR Axial Offset Anomaly (AOA) Guidelines”, EPRI Report TR-110070 (1999).
H. Kawamura and M. Furuya, “Effect of Water Chemistry on Crud Deposition Behavior on Heated Zircaloy-4 Surface in Simulated PWR Primary Water”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems 2010 (NPC2010), Paper No. 8.05, October 3–7, Quebec, Canada (2010).
H. Kawamura, H. Kanbe, M. Furuya, H. Kishida, and H. Hirano, “Effect of Zinc Injection on Corrosion Resistance of Zircaloy-2 Tube under Heat Transfer Condition”, Proc. 11th Environmental Degradation of Nuclear Materials — Light Water Reactor, Stevenson, USA, August 10–14, Stevenson, USA (2003), 617–628.
H. Kawamura and M. Furuya, “Effect of pH and Ni/Fe ratio on Crud Deposition Behavior on Heated Zircaloy-4 Surface in Simulated PWR Primary Water”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System 2008 (NPC’08), Paper No. P2–04, September 15–18, Berlin, Germany (2008).
C. Cheng and P. Frattini, “AOA Chemistry Diagnostics: Fuel Deposit Source Term Reduction by Elevated pH”, EPRI Report TR-110073 (1999).
J. Blok, S. Chauffriat, and P. Frattini, “Modeling the Axial Offset in PWRs”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System, (Chimie 2002), Paper No.69, April 22–26, Avignon, France (2002).
W. A. Byers, J. Deshon, G. P. Gary, J. F. Small, and J. B. Mcinvale, “Crud Metamorphosis at the Callaway Plant”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System 2006, Paper No.7–3, October 23–26, Jeju, Korea (2006).
W. Y. Maeng, B. S. Choi, D. K. Min, H. M. Kwon, I. K. Choi, J. W. Yeon, J. I. Kim, H. S. Woo, Y. K. Kim, and J. Y. Park, “The Status of AOA in Korean PWR and a study on the CRUD Deposition on Cladding Surface”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System 2008 (NPC’08), Paper No. L14–1, September 15–18, Berlin, Germany (2008).
C. Marks, K. Fruzzetti, and J. Deshon, “Reaction Kinetics of Primary Coolant Deposit Materials”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System 2008 (NPC-08), Paper No. L07–2, September 15–18, Berlin, Germany (2008).
P. J. Henshaw, J. C. McGuire, H. E. Sims, A. Tuson, S. Dickinson, and J. Deshon, “The Chemistry of Fuel Crud Deposits and Its Effect on AOA in PWR Plants”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System 2006, Paper No.7–1, October 23–26, Jeju, Korea (2006).
C. M. Criss and J. W. Cobble, J. Amer. Ceram. Soc., 86, (1964), 5385–5389.
C. M. Criss and J. W. Cobble, J. Amer. Ceram. Soc., 86, (1964), 5390–5396.
S. A. Attanasio and D. S. Morton, “Measurement of Nickel/Nickel Oxide Transition in Ni-Cr-Fe Alloy and Updated Data and Correlations to Quality the Effect of Aqueous Hydrogen on Primary Water SCC”, Proc. of 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems, Stevenson, (2003), 143–155.
Y. Sato et al., “Measurement of Concentration of Ni/NiO Equibrium Hydrogen and Evaluation for Radiation Source Reduction”, Proc. of Int. Conf. on Water Chemistry of Nuclear Reactor Systems 2006, Jeju, (2006).
B. Beverskog, “AOA Fuel Crud: A Theoretical Approach”, Proc. Int. Conf. on Water Chemistry of Nuclear Reactors System 2006, Paper No.7–2, October 23–26, Jeju, Korea (2006).
Author information
Authors and Affiliations
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2011 TMS (The Minerals, Metals & Materials Society)
About this paper
Cite this paper
Kawamura, H. (2011). Effect of DH Concentration on Crud Deposition on Heated Zircaloy-4 in Simulated PWR Primary Water. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_38
Download citation
DOI: https://doi.org/10.1007/978-3-319-48760-1_38
Publisher Name: Springer, Cham
Online ISBN: 978-3-319-48760-1
eBook Packages: Chemistry and Materials ScienceChemistry and Material Science (R0)