Characterization of Changes in Properties and Microstructure of Glassy Polymeric Carbon Following Au Ion Irradiation

Author:

Abunaemeh Malek Amir,Seif Mohamed,Yang Young,Wang Lumin,Chen Yanbin,Ojo Ibidapo,Muntele Claudiu,Ila Daryush

Abstract

AbstractThe TRISO fuel has been used in some of the Generation IV nuclear reactor designs [1,2]. It consists of a fuel kernel of UOx coated with several layers of materials with different functions. Pyrolytic carbon (PyC) is one of the materials in the layers. In this study we investigate the possibility of using Glassy Polymeric Carbon (GPC) as an alternative to PyC. In this work, we are comparing the changes in physical and microstructure properties of GPC after exposure to irradiation fluence of 5 MeV Au equivalent to a 1 displacement per atom (dpa) at samples prepared at 1000, 1500 and 2000°C. The GPC material is manufactured and tested at the Center for Irradiation Materials (CIM) at Alabama A&M University. Transmission electron microscopy (TEM), Rutherford backscattering spectroscopy (RBS), X-ray photoelectron spectroscopy (XPS) and Raman spectroscopy were used for the analysis.

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Reference8 articles.

1. Maximum heating rates for producing undistorted glassy carbon we determined by wedge-shaped samples;Maki;J. Mater. Res.,1996

2. 7. Fisher Jonathan , Dec 1996, “Active Crucible Bridgman system: Crucible characterization, RF Inductor Design And Model”, Dissertation, Alabama A&M University

3. 3.www.nextgenerationnuclearplant.com/i/triso.gif

4. Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance

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