Modeling of an air cooler with finned heat transfer tube banks using the RELAP5-3D code

被引:5
|
作者
Mochizuki, Hiroyasu [1 ]
机构
[1] Tokyo Inst Technol, Inst Innovat Res, Lab Adv Nucl Energy, Meguro Ku, 2-12-1 Ookayama, Tokyo 1528550, Japan
关键词
REACTOR;
D O I
10.1016/j.nucengdes.2020.110902
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The present paper proposes a calculation model of an air cooler using the RELAP5-3D code. Up to now, the modeling of an air cooler using RELAP5-3D was not described in detail, and there was a problem when calculating the decay heat removal system with the air cooler. Above all, the study of the heat transfer model for an air cooler with finned heat transfer tube banks is few. Since a decay heat removal system with air coolers is essential in liquid metal cooled fast nuclear reactors, it is anticipated how to model the air cooler using implemented heat transfer models in the RELAP5-3D code. The finned heat transfer tube is simulated with multiple bare tubes which have the equivalent heat transfer characteristics considering fin efficiency. Two kinds of simulations have been compared to the measured results of the "Monju" reactor under the forced and natural convection conditions in order to confirm the applicability of the proposed model. The simulation result under the forced convection condition is in good agreement with the test result except the operation mode under the natural convection. Since the simulation result under the natural convection condition overpredicts the test result, the surface area is lessened in order to decrease the heat transfer. As a result, good agreement has been obtained between the simulation and the test result under the natural convection condition. Sensitivity analysis has been performed for the cases where the outside diameter and the number of the simulated heat transfer tubes, and number of divisions of the calculation meshes are changed. It has been confirmed that there is almost no change in the total heat transfer rate even if various diameter tubes are used and the number of divisions is changed. The number of heat transfer tubes has a non-linear sensitivity to the removal heat rate.
引用
收藏
页数:14
相关论文
共 50 条
  • [1] HEAT TRANSFER BOUNDARY CONDITIONS IN THE RELAP5-3D CODE
    Riemke, Richard A.
    Davis, Cliff B.
    Schultz, Richard R.
    ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3, 2008, : 177 - 181
  • [2] THERMAL MODELING OF THE HTR-10 USING THE RELAP5-3D CODE
    Scari, Maria Elizabeth
    Costa, Antonella Lombardi
    Pereira, Claubia
    Mello da Silva, Clarysson Alberto
    Fortini Veloso, Maria Auxiliadora
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 2A, 2014,
  • [3] Modeling of corrosion-induced blockages on radiation heat transfer by using RELAP5-3D
    Khatry, Jivan
    Aydogan, Fatih
    Ilyas, Muhammad
    Houts, Michael
    PROGRESS IN NUCLEAR ENERGY, 2019, 112 : 123 - 134
  • [4] RECENT HYDRODYNAMICS IMPROVEMENTS TO THE RELAP5-3D CODE
    Riemke, Richard A.
    Davis, Cliff B.
    Schultz, Richard R.
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 3, 2009, : 353 - 357
  • [5] On the use of RELAP5-3D as a subchannel analysis code
    Memmott, Matthew
    Buongiorno, Jacopo
    Hejzlar, Pavel
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (04) : 807 - 815
  • [6] Modeling Moving Systems with RELAP5-3D
    Mesina, G. L.
    Aumiller, D. L.
    Buschman, F. X.
    Kyle, M. R.
    NUCLEAR SCIENCE AND ENGINEERING, 2016, 182 (01) : 83 - 95
  • [7] Special Issue on the RELAP5-3D Computer Code Foreword
    Mesina, G. L.
    NUCLEAR TECHNOLOGY, 2016, 193 (01) : III - IV
  • [8] Special Issue on the RELAP5-3D Computer Code Foreword
    Mesina, G. L.
    NUCLEAR SCIENCE AND ENGINEERING, 2016, 182 (01) : III - III
  • [9] Improvement of the RELAP5-3D condensation heat transfer model in the presence of noncondensable gases
    Anderson N.
    Sabharwall P.
    Sabharwall, Piyush (piyush.sabharwall@inl.gov), 1600, American Society of Mechanical Engineers (ASME) (142):
  • [10] Development of an Integrated Code System Using R5EXEC and RELAP5-3D
    Aumiller, David
    Buschman, Francis
    Tomlinson, Edward
    Gill, Daniel
    NUCLEAR TECHNOLOGY, 2016, 193 (01) : 183 - 199