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Hydride Induced Embrittlement on Zircaloy-4

Hydride Induced Embrittlement on Zircaloy-4. Doug Ogletree Glen Rose ISD Dr. Lin Shao (Texas A&M University) Dr. Wayne Kinnison (Texas A&M University--Kingsville). Radiation and Materials Science Group. This lab group works with particle accelerators.

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Hydride Induced Embrittlement on Zircaloy-4

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  1. Hydride Induced Embrittlementon Zircaloy-4 Doug Ogletree Glen Rose ISD Dr. Lin Shao (Texas A&M University) Dr. Wayne Kinnison (Texas A&M University--Kingsville)

  2. Radiation and Materials Science Group • This lab group works with particle accelerators. • Accelerators are used to simulate the reactor environment, speed up materials’ development and obtain fundamental understanding of those materials. • The team members are:

  3. Ion Beam Laboratory at TAMU • P.I.: Lin Shao • Visiting Faculty: Wayne Kinnison (TAMUK), Zhongyu Li (HEU) • Lab Manager: Mark Hollander • Graduate Students: Michael Martin, AsselAitkaliyeva (INL), Di Chen, Michael Myers(LLNL), George Wei, Tianyi Chen, Robert Balerio, Jing Wang, Michael General, Josey Wallace • Undergraduate Students: Richard Vega, Travis Smith, Lloyd Price, Lance Hill, Leanne Kristek, McIanAmos, Silas Marrs

  4. Overview • My research project involves the cladding material that covers fuel rods in a nuclear reactor. The material of interest in this project is Zircaloy-4. • The long term water-cooling of spent fuel rods, which are clad with zirconium alloys and come from nuclear reactors, elevates the requirement for their resistance to oxidation-related nodular corrosion. • Furthermore, oxidative reaction of zirconium with water releases hydrogen gas, which partly diffuses into the alloy and forms zirconium hydrides.

  5. Overview • The hydrides are less dense and are weaker mechanically than the alloy; their formation results in blistering and cracking of the cladding – a phenomenon known as hydrogen embrittlement.

  6. My Assignment • The project is interested in studying the effect of hydrogen accumulation in Zircaloy-4and how it causes the material to become brittle over time and try to understand how to lengthen the materials stability.

  7. Methods • I have prepared samples of Zircaloy-4 to implant hydrogen ions at various energy levels, which will result in the protons being implanted at different depths in the sample. • I will characterize the samples using nano- and micro-indentation techniques. • I will measure the depth of the indentations as a function of the applied force to help provide some insight into the embrittlement of the alloy.

  8. Work Performed • Soon after meeting the lab group, I got to first observe how to cut materials using a high precision saw.

  9. Polishing My Samples Next we polished the Zirc-4 using a polishing machine.

  10. Special Training Radiation Facility at Texas A&M University • I was then trained on how to operate the accelerator.

  11. Result of training on the 140 kV ion accelerator using 120 keV He ions.

  12. Next Steps • I will run SRIM software to get data on Zircaloy-4 to determine fluence levels. • I will use nano-indentation on one of my samples to determine a baseline. • I will begin the implantation of protons into the metal using different fluences. • http://www.youtube.com/watch?v=qjStle6_N8I • I will do the indentation measurements on the irradiated samples. • Finally, I will observe the irradiated samples using SEM.

  13. Summary • It is now up to individual power plants to safely take care of the spent nuclear fuel on site. • This will require storage for a long period of time. • This raises safety issues for the general population. • Therefore, this project will be one small piece in helping determine the continued use of Zircaloy-4 as a safe cladding material.

  14. Acknowledgements • TAMU E3 Program • National Science Foundation • Nuclear Power Institute • Dr. Lin Shao • Dr. Wayne Kinnison • Michael Martin • Richard Vega • Michael General • Josey Wallace

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