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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2015.1
- 수록면
- 559 - 566 (8page)
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초록· 키워드
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The thermalehydraulic characteristics for the CANadian Deuterium Uranium Flexible(CANFLEX)-burnable poison (BP) fuel channel, which is loaded with a BP at the center ringbased on the CANFLEX-RU (recycled uranium) fuel channel, are evaluated and comparedwith that of standard 37-element and CANFLEX-NU (natural uranium) fuel channels. Thedistributions of fuel temperature and critical channel power for the CANFLEX-BP fuelchannel are calculated using the NUclear Heat Transport CIRcuit ThermohydraulicsAnalysis Code (NUCIRC) code for various creep rate and burnup. CANFLEX-BP fuel channelhas been revealed to have a lower fuel temperature compared with that of a standard 37-element fuel channel, especially for high power channels. The critical channel power ofCANFLEX-BP fuel channel has increased by about 10%, relative to that of a standard 37-element fuel channel for 380 channels in a core, and has higher value relative to that ofthe CANFLEX-NU fuel channel except the channels in the outer core. This study has shownthat the use of a BP is feasible to enhance the thermal performance by the axial heat fluxdistribution, as well as the improvement of the reactor physical safety characteristics, andthus the reactor safety can be improved by the use of BP in a CANDU reactor.
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참고문헌 (13)
참고문헌 신청
G.H. Roh / 2011 / Improvement of power coefficient by using burnable poison in the CANDU reactor / Nucl. Eng. Design 241 : 1565 ~ 1578
J. H. Bae / 2010 / Comparison of fuel temperature characteristics between standard 37 element and CANFLEX fuel bundles / Korean Nuclear Society Autumn Meeting
J. H. Bae / 2012 / Thermal-hydraulic characteristics for fuel channels using burnable poison in the CANDU reactor / Korean Nuclear Society AutumnMeeting
J. H. Bae / 2013 / Fuel temperature characteristics for fuel channels using burnable poison in the CANDU reactor / Korean Nuclear Society Spring Meeting
J. H. Lau / 2004 / Design and qualification of the Bruce CANFLEX low void reactivity fuel bundle e an overview / Proceedings of the 25th CNS Annual Conference
J. H. Bae / 2010 / Comparison of fuel temperature characteristics between standard 37 element and CANFLEX fuel bundles / Korean Nuclear Society Autumn Meeting
J. H. Bae / 2012 / Thermal-hydraulic characteristics for fuel channels using burnable poison in the CANDU reactor / Korean Nuclear Society AutumnMeeting
J. H. Bae / 2013 / Fuel temperature characteristics for fuel channels using burnable poison in the CANDU reactor / Korean Nuclear Society Spring Meeting
J. H. Lau / 2004 / Design and qualification of the Bruce CANFLEX low void reactivity fuel bundle e an overview / Proceedings of the 25th CNS Annual Conference
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