ICONE11-36383 NUMERICAL PREDICTION OF ROD BUNDLE VOID FRACTION DISTRIBUTION WITH THE THREE-DIMENSIONAL MULTI-FLUID POROUS MEDIA BASED MODEL

Author(s):  
Zoran V. Stosic ◽  
Vladimir D. Stevanovic
Author(s):  
Kenichi Katono ◽  
Jun Nukaga ◽  
Takuji Nagayoshi ◽  
Kenichi Yasuda

We have been developing a void fraction distribution measurement technique using the three-dimensional (3D) time-averaged X-ray CT (computed tomography) system to understand two-phase flow behavior inside a fuel assembly for BWR (boiling water reactor) thermal hydraulic conditions of 7.2 MPa and 288 °C. Unlike CT images of a normal standstill object, we can obtain 3D CT images that are reconstructed from time-averaged X-ray projection data of the intermittent two-phase flow. We measured the 3D void fraction distribution in a vertical square (5 × 5) rod array that simulated a BWR fuel assembly in the air-water test. From the 3D time-averaged CT images, we confirmed that the void fraction at the center part of the channel box was higher than that near the channel box wall, and the local void fraction at the central region of a subchannel was higher than that at the gap region of the subchannel. A comparison of the volume-averaged void fractions evaluated by the developed X-ray CT system with those evaluated by a differential pressure transducer in a void fraction range from 0.05 to 0.40 showed satisfactory agreement within a difference of 0.03.


2014 ◽  
Vol 27 (5) ◽  
pp. 647-654 ◽  
Author(s):  
Takahiro ARAI ◽  
Masahiro FURUYA ◽  
Taizo KANAI ◽  
Kenetsu SHIRAKAWA ◽  
Yoshihisa NISHI

2015 ◽  
Vol 5 (1) ◽  
pp. 8-17
Author(s):  
Minh Giang Hoang ◽  
Tan Hung Hoang ◽  
Phu Khanh Nguyen

Recently, CTF, a version of COBRA-TF code is reviewed to validate its simulation models by several experiments such as Castellana 4x4 rod bundle, EPRI 5x5 bundle tests, PSBT bundle tests and TPTF experiment. These above experiments provide enthalpy, mass flux (Castellana), temperature (EPRI) and void fraction (PSBT, TPTF) at exit channel only. In order to simulate PWR rod bundle flow behavior, it is necessary to review CTF with more experiment in high pressure condition and it is found that the ENTEK BM facility is suitable for this purpose. The ENTEK BM facility is used to simulate Russia RBMK and VVER rod bundle two phase flow with pressure at 3 and 7 MPa and it gives measured void fraction distribution along the channel. This study focus on two points: (a) accuracy assessment between CTF’s void fraction distribution predictions versus experiment void fraction distributions and (b) investigation of void fraction prediction uncertainty from propagation of input deviations caused by measured accuracy.


Author(s):  
Takahiro ARAI ◽  
Atsushi UI ◽  
Masahiro FURUYA ◽  
Riichiro OKAWA ◽  
Tsugumasa IIYAMA ◽  
...  

2000 ◽  
Vol 20 (1Supplement) ◽  
pp. 333-334
Author(s):  
Nobuyuki TAKENAKA ◽  
Hitoshi ASANO ◽  
Terushige FUJII ◽  
Shunnsuke HAYAMA ◽  
Masahito MATSUBYASHI

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