CSR1000带肋子通道程序验证及分析

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基金项目:

国家国际科技合作专项基金(2012DFG61030)

Verification and Analysis of CSR1000 Subchannel Code with Wire Wrap Model

1. CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610041, China;
2. Department of Engineering Physics, Tsinghua University, Beijing, 100084, China

摘要: 超临界水冷堆燃料组件多采用绕肋进行自定位,绕肋对于组件热工水力特性的影响较为复杂。在超临界子通道程序ATHAS的基础上改进绕肋处理模块,并基于计算流体力学(CFD)工具对绕肋模型进行验证。改进后的子通道分析程序整体上能够反映出不同通道的变化趋势,对绕肋的几何参数变化也能做出较为合理的响应,证明绕肋模型正确;但在部分通道的预测上仍需要进一步改进。
- 超临界 /
- 子通道 /
- 绕肋 /
- 分布式阻力模型
Abstract: Wire wrapped rod bundles were generally adopted by SCWR fuel assembly design. The wire wraps may have complicated impact on the thermal hydraulic behaviors of the rod bundle. In this paper, some improvements have been made on the geometry identification of the wire wrap model based on the subchannel code ATHAS and the results were compared with the CFD code. The improved subchannel code can generally reflect the thermal hydraulic behaviors of each subchannel and make reasonable response to the variation of geometry factors. The improved subchannel code is physically reliable, however, more work needs to be done to improve its accuracy.
- Supercritical /
- Subchannel /
- Wire wrap /
- Distributed resistance model