NUMERICAL ANALYSIS OF HEAT TRANSFER TEST OF SUPERCRITICAL WATER IN A TUBE USING THE THREE-DIMENSIONAL TWO-FLUID MODEL CODE

被引:0
作者
Misawa, Takeharu [1 ]
Yoshida, Hiroyuki [1 ]
Tamai, Hidesada [1 ]
Takase, Kazuyuki [1 ]
机构
[1] Japan Atom Energy Agcy, Nucl Sci & Engn Directorate, Thermal & Fluid Engn Grp, Naka, Ibaraki, Japan
来源
ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3 | 2008年
关键词
D O I
暂无
中图分类号
TP [自动化技术、计算机技术];
学科分类号
0812 ;
摘要
The three-dimensional two-fluid model analysis code ACE-3D is developed in Japan Atomic Energy Agency for the thermal design procedure on two-phase flow thermal-hydraulics of light water-cooled reactors. In order to perform thermal hydraulic analysis of SCWR, ACE-3D is enhanced to supercritical pressure region. As a result, it is confirmed that transient change in subcritical and supercritical pressure region can be simulated smoothly using ACE-3D. that ACE-3D can predict the results of the past heat transfer experiment in the supercritical pressure condition, and that introduction of thermal conductivity effect of the wall restrains fluctuation of wall.
引用
收藏
页码:713 / 720
页数:8
相关论文
共 7 条
  • [1] Launder B. E., 1974, Letters in Heat and Mass Transfer, V1, P131, DOI 10.1016/0094-4548(74)90150-7
  • [2] MISAWA T, 2007, P 15 INT C NUCL ENG
  • [3] OHNUKI A, 2001, P 5 ORG MULT FLOW FO
  • [4] OKA Y, 2006, P ICAPP 06
  • [5] The Japan Society of Mechanical Engineers, 1999, JSME STEAM TABL
  • [6] FORCED CONVECTIVE HEAT-TRANSFER TO SUPERCRITICAL WATER FLOWING IN TUBES
    YAMAGATA, K
    YOSHIDA, S
    FUJII, T
    HASEGAWA, S
    NISHIKAW.K
    [J]. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1972, 15 (12) : 2575 - &
  • [7] YANG HQ, 1994, AIAA J, V32