모의 사용후 핵연료를 이용한 질화물 핵연료 소결체 제조
Fabrication of Nitride Fuel Pellet by Using Simulated Spent Nuclear Fuel
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In order to investigate a nitriding process of spent oxide fuel and the subsequent change in thermalproperties after nitriding, simulated spent fuel powder was converted into a nitride pellet with simulated fissionproduct elements through a carbothermic reduction process. Nitriding rate of simulated spent fuel was decreasedwith increasing of the amount of fission products. Contents of Ba and Sr in simulated spent fuel were decreasedafter the carbothermic reduction process. The thermal conductivity of the nitride pellet was decreased by an addi-tion of fission product element but was higher than that of the oxide fuel containing fission product elements.
Abstract
In order to investigate a nitriding process of spent oxide fuel and the subsequent change in thermalproperties after nitriding, simulated spent fuel powder was converted into a nitride pellet with simulated fissionproduct elements through a carbothermic reduction process. Nitriding rate of simulated spent fuel was decreasedwith increasing of the amount of fission products. Contents of Ba and Sr in simulated spent fuel were decreasedafter the carbothermic reduction process. The thermal conductivity of the nitride pellet was decreased by an addi-tion of fission product element but was higher than that of the oxide fuel containing fission product elements.
참고문헌 (25)
- L. C. Walters, , Prog. Nucl. Energy, 40, pp.513~ (2002)
- D. C. Crawford, , J. Nucl. Mater, 371, pp.202~ (2007)
- K. Minato, , J. Nucl. Mater, 320, pp.18~ (2003)
- Y. Arai, , J. Nucl. Mater, 344, pp.180~ (2005)
- H. Takano, , Prog. Nucl. Energy, 40, pp.473~ (2002)
- N. Hadibi-Olschewski, , J. Nucl. Mater, 188, pp.244~ (1992)
- Report to Congress on the Advanced Fuel Cycle Initiative, "US DOE", ~ (2003)
- US DOE, "A Technology Roadmap for Generation IV Nuclear Energy Systems", ~ (2002)
- B. A. Hilton, "ANS meeting on Nuclear Fuels and Structural Materials for the Next Generation Reactors", pp.4~8 (2006), Reno
- T. Muromura, , J. Nucl. Mater, 71, pp.65~ (1977)
- Y. Arai, , J. Nucl. Mater, 168, pp.280~ (1989)
- C. Ganguly, , J. Nucl. Mater, 178, pp.234~ (1991)
- D. D. Sood, , J. Nucl. Mater, 247, pp.293~ (1997)
- Hj. Matzke, "Science of advanced LMFBR fuels" (1986), North Holland, Amsterdam
- H. Blank, "Materials Science Technology in : Nuclear Materials, Ch.4. Nonoxide ceramic nuclear fuels" (1994), Weinheim
- J. W. Lee, "Technol", J. Nucl. Sci, 44, pp.597~ (2007)
- H. J. Ryu, , J. Phys. Chem.Solids, 66, pp.671~ (2005)
- K. H. Kang, , Thermochim.Acta, 455, pp.129~ (2007)
- M. S. Yang, , J. Nucl. Mater.In Press (2008)
- J. M. Shin, "Korean", J. Chem. Eng, 18, pp.1010~ (2001)
- R. Thetford, , J. Nucl. Mater, 320, pp.44~ (2003)
- P. G. Lucuta, , J. Nucl. Mater, 217, pp.279~ (1994)
- M. Sheindlin, , Rev. Sci.Instrum, 69, pp.1426~ (1998)
- Y. Aral, , J. Alloys Compd, 271, pp.602~ (1998)
