摘要
钠冷快堆能够提高铀资源的利用率,减少核废料的产生,是非常有前景的第四代核能系统堆型之一。同时,钠冷快堆也因其使用金属绕丝对燃料棒进行固定,具有更复杂的堆内构造,探究钠冷快堆堆芯内因绕丝而引起的搅浑效应对钠冷快堆的堆芯设计及安全分析具有重要意义。本文针对钠冷快堆的堆芯设计,采用CFD软件建立带绕丝的7根燃料棒束模型,针对大流量工况(工况1)、中流量工况(工况2)进行工况计算,根据流场的雷诺应力获得绕丝的湍流搅浑系数。并基于自主研发的子通道计算程序SAC-SUB建立相同的几何模型,将湍流搅浑系数输入子通道计算程序中,获得内通道、边通道、角通道温度分布,并将两种软件的计算结果进行了对比。对比结果表明,对于不同的通道而言,两种计算软件内通道的温度偏差最小(2.5℃),角通道的温度偏差最大(13.2℃)。对于不同的流量而言,中流量工况(工况2)温度偏差更小,最小温差只有0.8℃。该工作为后续快堆子通道分析搅浑系数的选取提供了技术基础。
The sodium-cooled fast reactor is one of the promising reactor types for the fourth generation of nuclear energy systems because it can improve the utilization of uranium resources and reduce the generation of nuclear waste. At the same time, sodium-cooled fast reactors have a more complex structure inside the reactor due to the use of metal wire winding to hold the fuel rods. In this paper, CFD software is used to model seven fuel rod bundles with winding wires for the core design of sodium-cooled fast reactors, and the turbulent mixing coefficients of winding wires are obtained based on the Reynolds stress of the flow field. Meanwhile, the same geometric model was established based on the self-developed sub-channel calculation program SAC-SUB(System Analysis Code-Subchannel model), and the turbulent mixing coefficients were input into the sub-channel calculation program to obtain the temperature distributions of the interior channel, edge channel and corner channel, and the calculation results of the two software were compared. The comparison results show that for different channels, the temperature deviation of the interior channel is the smallest(2.5 ℃) and the temperature deviation of the corner channel is the largest(13.2 ℃) for the two calculation software. For different flow rates, the temperature deviation is smaller for the medium flow rate condition(condition 2), with a minimum temperature difference of only 0.8 ℃. This work provides a technical basis for the selection of mixing coefficients for the subsequent fast stack sub-channel analysis.
作者
张珺
隋丹婷
彭晶
陆道纲
ZHANG Jun;SUI Danting;PENG Jing;LU Daogang(North China Electric Power University School of Nuclear Science and Engineering,Beijing 102206;Beijing Key Laboratory of Safety Technology for Passive Nuclear Energy,Beijing 102206)
出处
《核科学与工程》
CAS
CSCD
北大核心
2022年第6期1296-1304,共9页
Nuclear Science and Engineering
关键词
钠冷快堆
子通道分析
搅浑系数
CFD
Sodium cooled fast reactor
Sub-channel analysis
Mixing coefficient
CFD
