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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2015.1
- 수록면
- 85 - 93 (9page)
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초록· 키워드
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Background: 241Am, 243Am, and 237Np isotopes are among the most radiotoxic componentsof spent nuclear fuel. Recently, researchers have planned different incineration scenariosfor the highly radiotoxic elements of nuclear waste in critical reactors. Computationalmethods are widely used to predict burnup rates of such nuclear wastes that are usedunder fuel matrixes in critical reactors.
Methods: In this work, the Monte Carlo N-particle transport code was used to calculate theneutronic behavior of a transuranic (TRU)-bearing CANada Deuterium Uranium 6 reactor.
Results: The computational data showed that the 1.0% TRU-containing thorium-based fuelmatrix presents higher proliferation resistance and TRU depletion rate than the otherinvestigated fuel Matrixes. The fuel matrix includes higher negative temperature reactivitycoefficients as well.
Conclusion: The investigated thorium-based fuel matrix can be successfully used todecrease the production of highly radiotoxic isotopes
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참고문헌 (11)
참고문헌 신청
B. Hyland / 2011 / Scenarios for the transmutation of actinides in CANDU reactors / Nucl. Eng. Des 241 : 4794 ~ 4802
D.B. Pelowitz / 2008 / MCNPX User's Manual
International Atomic Energy Agency / 2005 / Thorium Fuel Cycledpotential Benefits and Challenges
K. Anantharaman / 2008 / Utilization of thorium in reactors / J. Nucl. Mater 383 : 119 ~ 121
M. Turkmen / 2012 / Use of Th and U in CANDU-6and ACR-700 on the once-through cycle: burnup, analyses, natural U requirement/saving and nuclear resource utilization / J. Nucl
D.B. Pelowitz / 2008 / MCNPX User's Manual
International Atomic Energy Agency / 2005 / Thorium Fuel Cycledpotential Benefits and Challenges
K. Anantharaman / 2008 / Utilization of thorium in reactors / J. Nucl. Mater 383 : 119 ~ 121
M. Turkmen / 2012 / Use of Th and U in CANDU-6and ACR-700 on the once-through cycle: burnup, analyses, natural U requirement/saving and nuclear resource utilization / J. Nucl
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