轴流铅铋泵的设计及其水力性能分析

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轴流铅铋泵的设计及其水力性能分析

更新时间：2025-07-09

- 轴流铅铋泵的设计及其水力性能分析
- Issue 11, Pages: 166-174(2020)
- 作者机构：
  
  西安交通大学动力工程多相流国家重点实验室
- 作者简介：
- 基金信息：
- DOI：
  CLC： TL433
- Published：2020
- 稿件说明：
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[J]. 2020, (11): 166-174.
DOI：

[J]. 2020, (11): 166-174. DOI：

摘要

为了研究铅铋合金泵合适的优化设计方案

基于叶片速度三角形和圆柱层无关性假设理论

设计了不同转速的轴流铅铋泵模型。利用Ansys CFX软件

构建了不同转速包含导叶的铅铋泵水力模型和无导叶的铅铋泵水力模型

通过SSTk-ω湍流模型模拟对比不同的转速以及有无导叶轮设计对轴流铅铋泵水力性能的影响。模拟结果表明:导叶轮是铅铋泵低流速设计的一个重要构件

可将转速为420r/min铅铋泵的叶轮出口冷却剂流速由4m/s降低到1.8m/s;泵内冷却剂和壁面间相对速度最高区域分布在叶片前缘泵壳侧

该流速会随泵轴转速的减小而降低;在低负荷条件下高转速铅铋泵比低转速铅铋泵拥有更好的流量扬程和效率性能

但是在0.8～1.2倍额定流量的高负荷工况条件下低转速铅铋泵比高转速铅铋泵拥有更高的效率和扬程性能。此项研究可为铅冷快堆的主泵设计优化提供一定的参考。

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雷驰,吴宏春,曹良志,周生诚,邵一穷.小型可运输长寿命铅铋冷却快堆堆芯设计研究[J].原子能科学技术,2019(08).

任芸,吴登昊,牟介刚,李晓俊.考虑旋转和曲率的湍流模型修正及应用[J].西安交通大学学报,2016(09).

徐一鸣,徐士鸣.核主泵惰转转速计算模型的比较[J].发电设备,2011(04).

阎畅,刘海涌,朱惠人,许都纯.带横流及旋流射流冲击换热的数值与实验研究[J].计算机仿真,2008(03).

韩国其,刘大恺.轴流泵后导叶几何参数的试验研究[J].河海大学学报,1989(01).

Tung Dong Cao Nguyen,Jiwon Choe,Bamidele Ebiwonjumi,Matthieu Lemaire,Deokjung Lee.Core design of long‐cycle small modular lead‐cooled fast reactor[J].International Journal of Energy Research,2019.

Jaesik Kwak,Hee Reyoung Kim.Development of innovative reactor‐integrated coolant system design concept for a small modular lead fast reactor[J].International Journal of Energy Research,2018.

Yonggang Lu,Rongsheng Zhu,Qiang Fu,Xiuli Wang,Ce An,Jing Chen.Research on the structure design of the LBE reactor coolant pump in the lead base heap[J].Nuclear Engineering and Technology,2019.

Shengcheng Zhou,Renzong Chen,Yiqiong Shao,Liangzhi Cao,Bofeng Bai,Hongchun Wu.Conceptual core design study of an innovative small transportable lead‐bismuth cooled fast reactor (SPARK) for remote power supply[J].International Journal of Energy Research,2018.

Leitai Shi,Tan Bing,Chenglong Wang,Wenxi Tian,Suizheng Qiu,Junmei Wu,G.H. Su.Experimental investigation of gas lift pump in a lead-bismuth eutectic loop[J].Nuclear Engineering and Design,2018.

Marcello Ferrini,Walter Borreani,Guglielmo Lomonaco,Fabrizio Magugliani.Design by theoretical and CFD analyses of a multi-blade screw pump evolving liquid lead for a Generation IV LFR[J].Nuclear Engineering and Design,2016.

Andrea Mangialardo,Walter Borreani,Guglielmo Lomonaco,Fabrizio Magugliani.Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors[J].Nuclear Engineering and Design,2014.

Small modular reactors: Simpler, safer, cheaper?[J].Energy,2012(1).

Jinsuo Zhang.A review of steel corrosion by liquid lead and lead–bismuth[J].Corrosion Science,2009(6).

K.L. Murty,I. Charit.Structural materials for Gen-IV nuclear reactors: Challenges and opportunities[J].Journal of Nuclear Materials,2008(1).

A.V. Zrodnikov,G.I. Toshinsky,O.G. Komlev,Yu.G. Dragunov,V.S. Stepanov,N.N. Klimov,V.N. Generalov,I.I. Kopytov,V.N. Krushelnitsky.Innovative nuclear technology based on modular multi-purpose lead–bismuth cooled fast reactors[J].Progress in Nuclear Energy,2007(2).

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