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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 377 - 383 (7page)
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Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paperanalyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in theCANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant voidreactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell withnatural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-averagechannel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversionratio is higher than that of the CANDU-6 reactor with natural uranium; and that the exit burnupincreases to 13400 MWd/tU. Thus, the simulation in this paper with the fuel in the 37-element bundlecell using discrete TU fuel pins can be considered to be applied in CANDU-6 reactor with adequatemodifications of the core structure and operating modes.
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참고문헌 (24)
참고문헌 신청
IAEA / Power Reactor Information System
G. Zhang / 2016 / Validation of thorium fuel benchmark by DRAGON code using WLUP library / Atomic Energy Sci. Technol 50(10):1828~1833
International Atomic Energy Agency / 2005 / Thorium Fuel Cycle: Potential Benefits and Challenges
Z. H. Zhang / 2010 / Technical advantage of HWR and the tentative plan for its development / China Nuclear Power 03(02):124~129
J.Q. Qian / 2003 / Characteristics and development of CANDU NPP unit / Chinese J. Nucl. Sci. Eng 23(03):193~120
G. Zhang / 2016 / Validation of thorium fuel benchmark by DRAGON code using WLUP library / Atomic Energy Sci. Technol 50(10):1828~1833
International Atomic Energy Agency / 2005 / Thorium Fuel Cycle: Potential Benefits and Challenges
Z. H. Zhang / 2010 / Technical advantage of HWR and the tentative plan for its development / China Nuclear Power 03(02):124~129
J.Q. Qian / 2003 / Characteristics and development of CANDU NPP unit / Chinese J. Nucl. Sci. Eng 23(03):193~120
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