Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (7): 70601-070601.doi: 10.11889/j.0253-3219.2020.hjs.43.070601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Analysis and optimization of flow distribution for the reactor core of China initiative accelerator driven system

Jun WEN1,2,Tianji PENG1,2,Xukai FAN1,Dajun FAN1,2,Wangsheng TIAN1,2,Dawei WANG1,2,3,Long GU1,2,3()   

  1. 1.Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
    2.School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing 100049, China
    3.School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China
  • Received:2020-03-09 Revised:2020-05-07 Online:2020-07-15 Published:2020-07-16
  • Contact: Long GU E-mail:gulong@impcas.ac.cn
  • About author:WEN Jun, male, born in 1995, graduated from Nanjing Tech University in 2016, master student, focusing on thermal hydraulics of LFR
  • Supported by:
    National Natural Science Foundation of China(11705255);Chinese Academy of Sciences “Light of West China” Program

Abstract: Background

Flow rate distribution is a significant study object in the reactor core design of China initiative accelerator driven system (CiADS). Reasonable flow rate distribution will ensure reactor core work safely.

Purpose

This study aims to optimize flow distribution in the coolant inlet area of each fuel assembly of CiADS so that the outlet temperature distribution is flat.

Method

Firstly, the top and bottom nozzle flow field were calculated by computational fluid dynamics (CFD) software. Secondly, based on the above results, the porous media model was employed to establish the flow and heat transfer analysis model of the whole reactor for numerical simulation of the flow distribution in the core, and the power coefficient was used as the reference for reactor core flow distribution.

Results

These calculation results show that the flow distribution and power coefficients are almost consistent, and the outlet temperature distribution for the fuel assemblies has been flattened. Both the pressure drop characteristics and coefficient of resistance properties of the top and bottom nozzle obtained by simulation provide the necessary parameters for analyzing the flow distribution of the core.

Conclusions

Based on the calculations, the coolant inlet area of each fuel assembly has been optimized. These calculation results show that the flow distribution and power coefficients are almost consistent, and the outlet temperature distribution for the fuel assemblies has been flattened. Thus, the fuel assembly could be operated under the safety conditions. Meanwhile, these results can provide some reference data for the subsequent hydraulic analysis.

Key words: Top nozzle, Bottom nozzle, Reactor core flow distribution, Porous media model, CFD

CLC Number: 

  • TL33