Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code-Reference-Cited by-同舟云学术

Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code

Published:2009-05 Issue:5 Volume:36 Page:583-589
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Jeong H.-Y.,Ha K.-S.,Kwon Y.-M.,Lee Y.-B.,Hahn D.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference24 articles.

1. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles – bundle friction factors, subchannel friction factors and mixing parameters;Cheng;Nucl. Eng. Des.,1986

2. Davis, A.L., 1979. SABRE I – A Computer Program for the Calculation of Three Dimensional Flows in Rod Clusters. AEEW-R 1057.

3. Domanus, H.M., Sha, W.T., 1978. Numerical Results for a Hexagonal Fuel Assembly with a Planar Blockage using the COMMIX-1A Computer Code. NUREG/CR-0483, US Nuclear Regulatory Commission.

4. Fluid flow through packed columns;Ergun;Chem. Eng. Prog.,1952

5. Wire-wrap models for subchannel blockage analysis;Ha;J. Korean Nucl. Soc.,2004

Cited by 10 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Experimental characterization of pressure and friction factor in an interior subchannel of a 61-pin wire-wrapped rod bundle with a porous blockage;Physics of Fluids;2023-11-01

2. Development of thermal hydraulic analysis code of annular fuel under flow blockage condition;Annals of Nuclear Energy;2021-02

3. A new method to investigate the boiling two-phase flows by a combination of the three-fluid and drift-flux models;Annals of Nuclear Energy;2020-07

4. Analysis of flow and heat transfer through a partially blocked fuel subassembly of fast breeder reactor;Progress in Nuclear Energy;2020-01

5. Investigation of heat transfer from a totally blocked fuel subassembly of fast breeder reactor with 7 and 19 pin bundles;Nuclear Engineering and Design;2018-11