Void Fraction Distribution and Mass/Energy Transfer Characteristics in Rod Bundle

2018 ◽  
Author(s):  
Jun-Yi Zhang ◽  
Xiao Yan ◽  
Ze-Jun Xiao ◽  
Yong-Ze Xu
Keyword(s):  
Energy Transfer ◽  
Void Fraction ◽  
Mass Energy ◽  
Transfer Characteristics ◽  
Rod Bundle ◽  
Void Fraction Distribution ◽  
Fraction Distribution

scholarly journals Development of Measurement Method of Void Fraction Distribution for Boiling Water Flow in Heated Rod Bundle

2014 ◽  
Vol 27 (5) ◽  
pp. 647-654 ◽  
Author(s):  
Takahiro ARAI ◽  
Masahiro FURUYA ◽  
Taizo KANAI ◽  
Kenetsu SHIRAKAWA ◽  
Yoshihisa NISHI
Keyword(s):  
Water Flow ◽  
Void Fraction ◽  
Measurement Method ◽  
Boiling Water ◽  
Rod Bundle ◽  
Void Fraction Distribution ◽  
Fraction Distribution

scholarly journals Investigation of CTF void fraction prediction by ENTEK BM experiment data

2015 ◽  
Vol 5 (1) ◽  
pp. 8-17
Author(s):  
Minh Giang Hoang ◽  
Tan Hung Hoang ◽  
Phu Khanh Nguyen
Keyword(s):  
Void Fraction ◽  
Accuracy Assessment ◽  
Flow Behavior ◽  
Simulation Models ◽  
Phase Flow ◽  
Experiment Data ◽  
Two Phase ◽  
Rod Bundle ◽  
Void Fraction Distribution ◽  
Fraction Distribution

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.

scholarly journals Void fraction distribution in a rod bundle with part-length rods via high-energy X-ray computed tomography

2021 ◽  
Author(s):  
Takahiro ARAI ◽  
Atsushi UI ◽  
Masahiro FURUYA ◽  
Riichiro OKAWA ◽  
Tsugumasa IIYAMA ◽  
...  
Keyword(s):  
Computed Tomography ◽  
Void Fraction ◽  
High Energy ◽  
X Ray ◽  
Rod Bundle ◽  
Void Fraction Distribution ◽  
Fraction Distribution ◽  
X Ray Computed

scholarly journals Void fraction distribution of gas-liquid two-phase flow in a rod bundle

2000 ◽  
Vol 20 (1Supplement) ◽  
pp. 333-334
Author(s):  
Nobuyuki TAKENAKA ◽  
Hitoshi ASANO ◽  
Terushige FUJII ◽  
Shunnsuke HAYAMA ◽  
Masahito MATSUBYASHI
Keyword(s):  
Void Fraction ◽  
Two Phase Flow ◽  
Phase Flow ◽  
Two Phase ◽  
Rod Bundle ◽  
Void Fraction Distribution ◽  
Fraction Distribution

High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures

2020 ◽  
Author(s):  
Takahiro Arai ◽  
Atsushi Ui ◽  
Masahiro Furuya ◽  
Riichiro Okawa ◽  
Tsugumasa Iiyama ◽  
...  
Keyword(s):  
Void Fraction ◽  
High Energy ◽  
Uniform Heat Flux ◽  
Two Phase ◽  
Cross Sectional ◽  
Rod Bundle ◽  
Wide Range ◽  
Void Fraction Distribution ◽  
Fraction Distribution ◽  
Heated Length

Abstract A boiling experiment was conducted to acquire a three-dimensional void fraction distribution in a rod bundle with part length rods. The test section was a 5 × 5 heated rod bundle that partially simulated a BWR rod bundle, and three PLRs were arranged together in the corner. The heated length of the full-length rod was 3.71 m, which is equal in length to an actual fuel rod in BWRs, whereas the heated length of the PLR was 1.85 m. The rod bundle exhibited an axially and radially uniform heat flux. Further, the local void fraction was quantified by normalizing the intensities in the CT images of the boiling two-phase flow with those obtained under the liquid-phase and gas-phase conditions. The cross-sectional void fraction distribution was acquired at six height levels. The experimental results exhibited the void distribution around PLRs with respect to a wide range of flow conditions, inlet temperatures, inlet flow rates, bundle thermal powers, and system pressures.

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