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
- 2009.1
- 수록면
- 677 - 690 (14page)
이용수
초록· 키워드
오류제보하기
A previous study demonstrated that the two-row fuel assembly has much more favorable neutron-physical and thermalhydraulic
behavior than the conventional one-row fuel assemblies. Based on the newly developed two-row fuel assembly, an
SCWR core is proposed and analyzed.
The performance of the proposed core is investigated with 3-D coupled neutron-physical and thermal-hydraulic
calculations. During the coupling procedure, the thermal-hydraulic behavior is analyzed using a sub-channel analysis code
and the neutron-physical performance is computed with a 3-D diffusion code. This paper presents the main results achieved
thus far related to the distribution of some neutronic and thermal-hydraulic parameters. It shows that with adjustment of the
coolant and moderator mass flow in different assemblies, promising neutron-physical and thermal-hydraulic behavior of the
SCWR core is achieved. A sensitivity study of the heat transfer correlation is also performed.
Since the pin power in fuel assemblies can be non-uniform, a sub-channel analysis is necessary in order to investigate the
detailed distribution of thermal-hydraulic parameters in the hottest fuel assembly. The sub-channel analysis is performed
based on the bundle averaged parameters obtained with the core analysis. With the sub-channel analysis approach, more
precise evaluation of the hot channel factor and maximum cladding surface temperature can be achieved. The difference in
the results obtained with both the sub-channel analysis and the fuel assembly homogenized method confirms the importance
of the sub-channel analysis.
목차
등록된 정보가 없습니다.
참고문헌 (14)
참고문헌 신청
A. Yamaji / 2005 / Evaluation of the Nominal Peak Cladding Surface Temperature of the Super LWR with Sub-channel Analyses / Proceedings of GLOBAL 2005
A. Yamaji / 2005 / Improved Core Design of the High Temperature Supercritical-Pressure Light Water Reactor / Annals of Nuclear Energy 32 : 651 ~
C. Waata / 2005 / Results of a Coupled Neutronics and thermal-hydraulics Analysis of a HPLWR Fuel Assembly / Proceedings of 2005 International Congress on Advances in Nuclear Power
K. Kamei / 2005 / Fuel and Core Design of Super LWR with Stainless Steel Cladding / Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP ’05)
K. Rehme / 1992 / The Structure of Turbulence in Rod Bundles and the Implications on Natural Mixing between the Subchannels / Int. Journal of Heat and Mass Transfer 35 : 567
A. Yamaji / 2005 / Improved Core Design of the High Temperature Supercritical-Pressure Light Water Reactor / Annals of Nuclear Energy 32 : 651 ~
C. Waata / 2005 / Results of a Coupled Neutronics and thermal-hydraulics Analysis of a HPLWR Fuel Assembly / Proceedings of 2005 International Congress on Advances in Nuclear Power
K. Kamei / 2005 / Fuel and Core Design of Super LWR with Stainless Steel Cladding / Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP ’05)
K. Rehme / 1992 / The Structure of Turbulence in Rod Bundles and the Implications on Natural Mixing between the Subchannels / Int. Journal of Heat and Mass Transfer 35 : 567
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
〈학술논문〉 초임계압수 냉각로 노심열수력 특성 예비평가
대한기계학회 춘추학술대회
2008 .04
-
RESEARCH ACTIVITIES ON A SUPERCRITICAL PRESSURE WATER REACTOR IN KOREA
Nuclear Engineering and Technology
2007 .01
-
Thermal - Hydraulic Analysis of A Wire - Spacer Fuel Assembly
한국유체기계학회 학술대회 논문집
2004 .12
-
Three-dimensional Core Design of a Super Fast Reactor with a High Power Density
Nuclear Engineering and Technology
2010 .01
-
Seismic behavior of fuel assembly for pressurized water reactor
Structural engineering and mechanics : An international journal
1994 .01
-
초임계압수냉각원자로(SCWR) 기술 타당성 평가
한국에너지학회 학술발표회
2008 .10
-
고 발전효율의 초임계압수냉각원자로(SCWR) 개발 현황
한국에너지학회 학술발표회
2008 .10
-
ANSYS를 이용한 개량핵연료 집합체 상세모델 개발에 관한 연구
대한기계학회 춘추학술대회
2004 .10
-
OPR-1000 원자로의 출력증강을 위한 18×18 원통형 핵연료의 열수력적 타당성 평가
대한기계학회 춘추학술대회
2009 .11
-
Assembly Modeling
한국CDE학회지
1997 .12
-
자유낙하에 의한 경수로용 핵연료집합체의 동적 거동 해석
대한기계학회 춘추학술대회
2006 .11
-
ASSESSMENT OF STABILITY MAPS FOR HEATED CHANNELS WITH SUPERCRITICAL FLUIDS VERSUS THE PREDICTIONS OF A SYSTEM CODE
Nuclear Engineering and Technology
2007 .01
-
플라스틱 광섬유 센서를 이용한 핵 연료의 열중성자 분포도 측정
센서학회지
2009 .01
-
Conceptual design of a high neutron fl ux research reactor core with low enriched uranium fuel and low plutonium production
Nuclear Engineering and Technology
2020 .01
-
Study of fission gas products effect on thermal hydraulics of the WWER1000 with enhanced subchannel method
Advances in energy research
2017 .01
-
경수로 원전연료용 지지격자체의 LASER 용접부위 평가
대한용접학회 특별강연 및 학술발표대회 개요집
2004 .11
-
Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing
Nuclear Engineering and Technology
2019 .01
-
냉중성자 수조내기기 설치 및 유지관리
한국기계기술학회지
2014 .01
-
Flow and Convective Heat Transfer Analysis Using RANS for A Wire-Wrapped Fuel Assembly
Journal of Mechanical Science and Technology
2006 .09
-
Shock Thermal and Hydraulic Processes under Pulse Heat Power Surge in a Channel
Heat Transfer Conference
1998 .08
이 논문의 저자 정보
최근 본 자료
댓글(0)
0