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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 1,208 - 1,212 (5page)
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초록· 키워드
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Knowledge on fuel enthalpyand its temperature derivative, the heat capacity, are important quantities in determination of fuel behavior in normal reactor operation and reactor transients. The aim of this study is to compare the heat capacity of oxide and nitrite fuels by using Einstein-Debye approximation. A simple analytical expressionwas performed to calculate the heat capacityof fuels. Totest the validityand reliability, the calculatedformulas werecomparedto published results for various nuclear fuels including UO2, ThO2, PuO2 and UN. Calculated formulas yielded results in consistent with literature
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참고문헌 (61)
참고문헌 신청
S. Peng / 1994 / Heat capacity of actinide dioxides / J. Nucl. Mater 210:115~122
C. Ronchi / 2007 / Thermophysical properties affecting safety and performance of nuclear fuel / High Temp 45:552~571
Y. Yun / 2011 / First-principles design of next-generation nuclear fuels / MRS Bull 36:178~184
J. K. Fink / 2000 / J. Nucl. Mater 279:1~18
J. J. Carbajo / 2001 / J. Nucl. Mater 299:181~198
C. Ronchi / 2007 / Thermophysical properties affecting safety and performance of nuclear fuel / High Temp 45:552~571
Y. Yun / 2011 / First-principles design of next-generation nuclear fuels / MRS Bull 36:178~184
J. K. Fink / 2000 / J. Nucl. Mater 279:1~18
J. J. Carbajo / 2001 / J. Nucl. Mater 299:181~198
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