VOID FRACTION IN SIMULATED BWR FUEL ASSEMBLY .1. SPACER EFFECT ON VOID FRACTION AND ANALYSIS WITHOUT CROSS-FLOW

被引：2
|
作者：
MOROOKA, S
SHIRAKAWA, K
ISHIZUKA, T
YOSHIMURA, K
MAWATARI, K
机构：
来源：
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN | 1991年 / 33卷 / 06期
关键词：
2 PHASE FLOW; VOID FRACTION; X-RAY CT SCANNER; FLOW PATTERN; MEASUREMENT; EXPERIMENTAL DATA; STEAM; WATER; ROD BUNDLE; BWR TYPE REACTORS; SPACER; SUBCHANNEL ANALYSIS;
D O I：
10.3327/jaesj.33.585
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：
Void measurement of a vertical 4 x 4 rod bundle has been conducted behind a spacer in a steam-water two-phase flow using an advanced X-ray CT scanner and one-dimensional single subchannel analysis without a cross-flow was done. It was found from the experimental results that the cross-sectional averaged void fraction data behind the spacer could be predicted by the drift-flux model, that the spacer has a negligible effect on the cross-sectional averaged void fraction and that EPRI correlation made it possible to accurately predict the void data. In addition, the simplified single subchannel analysis without the cross-flow between subchannels gave good agreement with data of center subchannels in a quality range of 5% or more. However, the analysis predicted higher void fraction than experimental results in the corner subchannel.
引用
收藏
页码：585 / 593
页数：9
相关论文
共 50 条
  • [21] Effect of flow regime and void fraction on tube bundle vibration
    Taylor, CE
    Pettigrew, MJ
    FLOW-INDUCED VIBRATION, 2000, : 529 - 536
  • [22] Effect of flow regime and void fraction on tube bundle vibration
    Taylor, CE
    Pettigrew, MJ
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2001, 123 (04): : 407 - 413
  • [23] Research on void fraction models for vertically upward two-phase cross-flow in horizontal tube bundle
    Jiang, N.-B., 2013, Atomic Energy Press (34):
  • [24] VOID FRACTION DISTRIBUTION IN A BOILING WATER-REACTOR FUEL ASSEMBLY AND THE EVALUATION OF SUBCHANNEL ANALYSIS CODES
    INOUE, A
    FUTAKUCHI, M
    YAGI, M
    MITSUTAKE, T
    MOROOKA, SI
    NUCLEAR TECHNOLOGY, 1995, 112 (03) : 388 - 400
  • [25] PRESSURIZED-WATER REACTOR-FUEL ASSEMBLY SUBCHANNEL VOID FRACTION MEASUREMENT
    AKIYAMA, Y
    HORI, K
    MIYAZAKI, K
    MISHIMA, K
    SUGIYAMA, S
    NUCLEAR TECHNOLOGY, 1995, 112 (03) : 412 - 421
  • [26] Measurement of the void fraction in a channel simulating the HANARO fuel assembly using neutron radiography
    Lim, IC
    Sim, CM
    Cha, JE
    Choi, YS
    Takenaka, N
    Saito, Y
    Jun, BJ
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2005, 542 (1-3): : 181 - 186
  • [27] A multiscale approach to analyze the effect of radial void fraction distributions on BWR neutronic lattice parameters
    Price, Dean
    Kozlowski, Tomasz
    ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [28] Effect of U-bend on void fraction in subcooled boiling flow
    Pan, Yue
    Zhai, Yuling
    Li, Zhouhang
    INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2023, 143
  • [29] Analysis of theoretical models for the void fraction fluctuations in two phase flow
    Roston, G. B.
    Ascheri, M. E.
    Martin, M. C.
    Pizarro, R.
    FMA'08: PROCEEDINGS OF THE 6TH IASME/WSEAS INTERNATIONAL CONFERENCE ON FLUID MECHANICS AND AERODYNAMICS: NEW ASPECTS OF FLUID MECHANICS AND AERODYNAMICS, 2008, : 158 - 162
  • [30] Void fraction in a co-current two-phase flow through a prototypical PWR spent fuel assembly
    Brillant, G.
    Martin, J.
    NUCLEAR ENGINEERING AND DESIGN, 2021, 383
12345