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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 674 - 680 (7page)
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초록· 키워드
오류제보하기
We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (ThþPu)O2 mixture. We determined the critical height at which the reactorapproached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core fueled with mixed (ThþPu)O2, achieved about 24% higher fuel cycle length than the UO2 case. It also enhanced safeguard security by burning Pu isotopes. The results were compared with previously published papers and good agreements were found.
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참고문헌 (13)
참고문헌 신청
2012 / Overview of generation IV (gen IV) reactor designs
2003 / IAEA TECDOC 1382, Evaluation of High Temperatures Gas Cooled Reactors Performance: Benchmark Analyses Related to Initial Testing of HTTR
Andrew C. Kadak / 2005 / A future for nuclear Energy e pebble bed reactors, Massachusetts Institute of Technology / Int. J. Crit. Infrastruct 1(4)
Karen Graham / Nuclear experts voice safety concerns over pebble-bed reactors
2000 / IAEA TECDOC 1155, Thorium Based Fuel Options for the Generation of Electricity
2003 / IAEA TECDOC 1382, Evaluation of High Temperatures Gas Cooled Reactors Performance: Benchmark Analyses Related to Initial Testing of HTTR
Andrew C. Kadak / 2005 / A future for nuclear Energy e pebble bed reactors, Massachusetts Institute of Technology / Int. J. Crit. Infrastruct 1(4)
Karen Graham / Nuclear experts voice safety concerns over pebble-bed reactors
2000 / IAEA TECDOC 1155, Thorium Based Fuel Options for the Generation of Electricity
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