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
- 2015.4
- 수록면
- 284 - 292 (9page)
이용수
초록· 키워드
오류제보하기
A numerical calculation with the commercial computational fluid dynamics code CFX-14.0 was conducted for a test facility simulating the Canadian deuterium uranium moderator thermal?hydraulics. Two kinds of moderator thermal?hydraulic tests at Stern Laboratories Inc. were performed in the full geometric configuration of the Canadian deuterium uranium moderator circulating vessel, which is called a calandria tank, housing a matrix of horizontal rod bundles simulating calandria tubes. The first of these tests is the pressure drop measurement of a cross flow in the horizontal rod bundles. The other is the local temperature measurement on the cross section of the horizontal cylinder vessel simulating the calandria system. In the present study, the full geometric details of the calandria tank are incorporated in the grid generation of the computational domain to which the boundary conditions for each experiment are applied. The numerical solutions are reviewed and compared with the available test data.
목차
등록된 정보가 없습니다.
참고문헌 (18)
참고문헌 신청
G.E. Gillespie / 1981 / An experimental investigation of heat transfer from a reactor fuel channel: to surrounding water / Proceedings of the 2nd Annual Conference of the Canadian Nuclear Society
H.Z. Fan / 2009 / Enhancement of the moderator subcooling margin using glass-peened calandria tubes in CANDU reactors / Proceedings of the 30th Annual Conference of the Canadian Nuclear Society
R.G. Huget / 1989 / Status of physical and numerical modelling of CANDU moderator circulation / Proceedings of the 10th Annual Conference of the Canadian Nuclear Society
R. G. Huget / 1990 / MODTURC-CLAS: an efficient code for analyses of moderator circulation in CANDU reactors / Proceedings of the 3rd International Conference on Simulation Methods in Nuclear Engineering
H. F. Khartabil / 2000 / Three-Dimensional Moderator Circulation Experimental Program for Validation of CFD Code MODTURC_CLAS / Proceedings of the 21st Nuclear Simulation Symposium
H.Z. Fan / 2009 / Enhancement of the moderator subcooling margin using glass-peened calandria tubes in CANDU reactors / Proceedings of the 30th Annual Conference of the Canadian Nuclear Society
R.G. Huget / 1989 / Status of physical and numerical modelling of CANDU moderator circulation / Proceedings of the 10th Annual Conference of the Canadian Nuclear Society
R. G. Huget / 1990 / MODTURC-CLAS: an efficient code for analyses of moderator circulation in CANDU reactors / Proceedings of the 3rd International Conference on Simulation Methods in Nuclear Engineering
H. F. Khartabil / 2000 / Three-Dimensional Moderator Circulation Experimental Program for Validation of CFD Code MODTURC_CLAS / Proceedings of the 21st Nuclear Simulation Symposium
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
푸리에변환 적외선분광 설비를 활용한 보호막 공정의 수소, 중수소 농도의 구분 계측 및 정량화를 통한 소자 특성 안정화
대한전자공학회 학술대회
2021 .11
-
Systems Analyses of Alternative Technologies for the Recovery of Seawater Uranium
방사성폐기물학회지
2018 .01
-
A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters
Nuclear Engineering and Technology
2016 .06
-
Dynamics of Deuterium Desorption from SS316LN
한국가스학회 학술대회논문집
2016 .06
-
Removal of Uranium from Uranium Plant Wastewater Using Zero-Valent Iron in an Ultrasonic Field
Nuclear Engineering and Technology
2016 .06
-
Numerical Simulation on Membrane Emulsification – Study the Effect of Process Parameters on Droplet Size
한국유체기계학회 학술대회 논문집
2024 .07
-
Modeling the sensitivity of hydrogeological parameters associated with leaching of uranium transport in an unsaturated porous medium
Environmental Engineering Research
2018 .12
-
A method for purifying reprocessed uranium from even isotopes under conditions of multiple recycle
Nuclear Engineering and Technology
2022 .10
-
Production of uranium tetrafluoride from the effluent generated in the reconversion via ammonium uranyl carbonate
Nuclear Engineering and Technology
2017 .01
-
Measurement of deuterium concentration in heavy water utilizing prompt gamma neutron activation analysis (PGNAA) in comparison with MCNPX simulation results
Nuclear Engineering and Technology
2022 .11
-
고압 중수소 어닐링을 통한 SiO2 절연체의 균일성 개선
전기전자재료학회논문지
2024 .03
-
NEUTRONICS INVESTIGATION OF CANADA DEUTERIUM URANIUM 6 REACTOR FUELED (TRANSURANICeTH) O2 USING A COMPUTATIONAL METHOD
Nuclear Engineering and Technology
2015 .01
-
Laboratory Establishment for Measuring Uranium Radioactivity in Urine
한국방사성폐기물학회 학술대회
2019 .01
-
Improving the Neutronic Characteristics of a Boiling Water Reactor by Using Uranium Zirconium Hydride Fuel Instead of Uranium Dioxide Fuel
Nuclear Engineering and Technology
2016 .06
-
Impact Analysis on the Uranium Evaluation Related to the Collecting Location of the Environmental Sample
한국방사성폐기물학회 학술대회
2017 .01
-
Experimental study of the influence of borehole parameters on prompt fission neutron uranium logging and its corrections
Nuclear Engineering and Technology
2024 .08
-
Study of Chemical Separation Methods for the Treatment of a Uranium Containing Process Effluent
한국방사성폐기물학회 학술대회
2018 .01
-
Microstructure dependence of plasma-induced surface modification in polycrystalline pure tungsten
한국소성가공학회 학술대회 논문집
2021 .05
-
우라늄 농축도에 따른 최적 감속재와 연료 질량비 분석
한국에너지학회 학술발표회
2015 .04
-
국내 학교 체육관의 실내 PM2.5 저감을 위한 CFD 분석 연구
한국생태환경건축학회 학술발표대회 논문집
2021 .05
이 논문의 저자 정보
최근 본 자료
댓글(0)
0