지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2008.1
- 수록면
- 409 - 418 (10page)
이용수
초록· 키워드
오류제보하기
Because the interaction layers that form between U-Mo particles and the Al matrix degrade the thermal properties of U-Mo/Al
dispersion fuel, an investigation was undertaken of the undesirable feedback effect between an interaction layer growth and a
centerline temperature increase for dispersion fuel. The radial temperature distribution due to interaction layer growth during
irradiation was calculated iteratively in relation to changes in the volume fractions, the thermal conductivities of the
constituents, and the oxide thickness with the burnup. The interaction layer growth, which is estimated on the basis of the
temperature calculations, showed a reasonable agreement with the post-irradiation examination results of the U-Mo/Al
dispersion fuel rods irradiated at the HANARO reactor. The U-Mo particle size was found to be a dominant factor that
determined the fuel temperature during irradiation. Dispersion fuel with larger U-Mo particles revealed lower levels of both
the interaction layer formation and the fuel temperature increase. The results confirm that the use of large U-Mo particles
appears to be an effective way of mitigating the thermal degradation of U-Mo/Al dispersion fuel.
목차
등록된 정보가 없습니다.
참고문헌 (23)
참고문헌 신청
A. Leenaers / 2004 / Post-irradiation Examination of Uranium?7 wt% Molybdenum Atomized Dispersion Fuel / J. Nucl. Mater 335 (39)
C.K. Kim / 2003 / of the Back-end Optional Advanced Research Reactor Fuel Development in Korea / Proc. RERTR-2003 Inter. Mtg., Chicago
C.K. Kim / 2005 / Progress of the KOMO-3 Irradiation Test for Various U-Mo Dispersion and Monolithic Fuels to Overcome the Interaction Problem in U-Mo/Al Dispersion Fuel / Inter. Mtg.,
CHANG KYU KIM / 2007 / USE OF A CENTRIFUGAL ATOMIZATION PROCESS IN THE DEVELOPMENT OF RESEARCH REACTOR FUEL / Nuclear Engineering and Technology 39 (5) : 617 ~ 626
D.B. Lee / 1997 / Thermal Compatibility Studies of Unirradiated U-Mo Alloys Dispersed in Aluminum / J. Nucl. Mater 250 (79)
C.K. Kim / 2003 / of the Back-end Optional Advanced Research Reactor Fuel Development in Korea / Proc. RERTR-2003 Inter. Mtg., Chicago
C.K. Kim / 2005 / Progress of the KOMO-3 Irradiation Test for Various U-Mo Dispersion and Monolithic Fuels to Overcome the Interaction Problem in U-Mo/Al Dispersion Fuel / Inter. Mtg.,
CHANG KYU KIM / 2007 / USE OF A CENTRIFUGAL ATOMIZATION PROCESS IN THE DEVELOPMENT OF RESEARCH REACTOR FUEL / Nuclear Engineering and Technology 39 (5) : 617 ~ 626
D.B. Lee / 1997 / Thermal Compatibility Studies of Unirradiated U-Mo Alloys Dispersed in Aluminum / J. Nucl. Mater 250 (79)
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Influence of Fuel-matrix Interaction on the Breakaway Swelling of U-Mo Dispersion Fuel in Al
Nuclear Engineering and Technology
2014 .01
-
Post-irradiation Analyses of U-Mo Dispersion Fuel Rods of KOMO Tests at HANARO
Nuclear Engineering and Technology
2013 .01
-
Application of Laser Ablation Inductively Coupled Plasma Mass Spectrometry for Characterization of U-7Mo/Al-5Si Dispersion Fuels
Nuclear Engineering and Technology
2017 .01
-
Analysis on the post-irradiation examination of the HANARO miniplate-1 irradiation test for kijang research reactor
Nuclear Engineering and Technology
2017 .01
-
Modeling of Interaction Layer Growth between U-Mo Particles and an Al Matrix
Nuclear Engineering and Technology
2013 .01
-
Irradiation Performance of U-Mo Monolithic Fuel
Nuclear Engineering and Technology
2014 .01
-
Comparative Analysis of Structural Changes in U-Mo Dispersed Fuel of Full-size Fuel Elements and Mini-rods Irradiated in the MIR Reactor
Nuclear Engineering and Technology
2013 .01
-
USE OF A CENTRIFUGAL ATOMIZATION PROCESS IN THE DEVELOPMENT OF RESEARCH REACTOR FUEL
Nuclear Engineering and Technology
2007 .01
-
Scanning Electron Microscopy Analysis of Fuel/Matrix Interaction Layers in Highly-Irradiated U–Mo Dispersion Fuel Plates with Al and Al–Si Alloy Matrices
Nuclear Engineering and Technology
2014 .01
-
A Microstructural Model of the Thermal Conductivity of Dispersion Type Fuels with a Fuel Matrix Interaction Layer
Nuclear Engineering and Technology
2013 .01
-
MOS 구조의 특성
대한전기학회 학술대회 논문집
1986 .07
-
동작속도가 빠른 Mo2N/Mo 게이트 MOS 집적회로 ( High Speed Mo2N/Mo-Gate MOS Integrated Circuit )
전자공학회지
1985 .07
-
D MOS , V MOS tr. 등 특수구조를 갖는 MOS소자의 설계
대한전자공학회 단기강좌
1983 .01
-
MOS Processing
대한전자공학회 단기강좌
1982 .01
-
Effect of central hole on fuel temperature distribution
Nuclear Engineering and Technology
2017 .01
-
연료품질 및 연비계산 방법 변화에 따른 연비특성 분석
동력시스템공학회지
2016 .08
-
2.25Cr-1Mo강에서 Mo 함량에 따른 고온환경에서의 용접부 미세조직 및 물성변화
대한용접학회 특별강연 및 학술발표대회 개요집
2010 .05
-
Electrochemical Stability of Co-Mo and Ni-Mo Hydrogen Electrodes for Alkaline Fuel Cells
Fabrication and Characterization of Advanced Materials
1995 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0