Research on void drift between rod bundle subchannels

Shasha Liu; Zaiyong Ma; Bo Pang; Rui Zhang; Luteng Zhang; Quanyao Ren; Liangming Pan

Nuclear Engineering and Technology (Aug 2024)

Research on void drift between rod bundle subchannels

Shasha Liu,
Zaiyong Ma,
Bo Pang,
Rui Zhang,
Luteng Zhang,
Quanyao Ren,
Liangming Pan

Affiliations

Shasha Liu: Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, PR China; Department of Nuclear Engineering and Nuclear Technology, Chongqing University, Chongqing, 400044, PR China
Zaiyong Ma: Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, PR China; Department of Nuclear Engineering and Nuclear Technology, Chongqing University, Chongqing, 400044, PR China; Corresponding author. Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, PR China.
Bo Pang: Department of Nuclear Science and Technology, Shenzhen University, Shenzhen, 518060, PR China; Corresponding author.
Rui Zhang: Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, PR China; Department of Nuclear Engineering and Nuclear Technology, Chongqing University, Chongqing, 400044, PR China
Luteng Zhang: Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, PR China; Department of Nuclear Engineering and Nuclear Technology, Chongqing University, Chongqing, 400044, PR China
Quanyao Ren: Science and Technology on Reactor System Design Technology Laborator, Chengdu, 610041, PR China
Liangming Pan: Key Laboratory of Low-Grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing, 400044, PR China; Department of Nuclear Engineering and Nuclear Technology, Chongqing University, Chongqing, 400044, PR China

Journal volume & issue: Vol. 56, no. 8
pp. 3330 – 3334

Abstract

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Void drift between subchannels in a rod bundle is a crucial phenomenon affecting the calculation accuracy of thermal-hydraulic parameters in SMRs. It holds significant importance in enhancing the precision of safety analysis for SMRs. Existing research on experiment and model of void drift between rod bundle subchannels is relatively rare, and the accuracy of model calculations requires improvement. In this study, experiments on gas-liquid two-phase non-equilibrium flow were conducted to measure the redistribution of two-phase flow induced by void drift in a 1 × 2 rod bundle. The experiment results indicated that in bubby flow regime with void fraction less than 0.3, the void diffusion coefficient showed little variation with changes in void fraction. However, in slug flow and annular flow regimes with void fraction exceeding 0.3, the void diffusion coefficient significantly increased with an increase in void fraction. Furthermore, a new void drift model was developed and validated based on a subchannel code. The overall predicted uncertainty for the outlet void fraction in the rod bundle benchmark was less than 13%.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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