Flow and heat transfer behaviors for double-walled-straight-tube heat exchanger of HLM loop

被引：11

作者：

Liu, Shuyong ^{[1
,2
]}

Jin, Ming ^{[1
]}

Lyu, Kefeng ^{[1
]}

Zhou, Tao ^{[1
]}

Zhao, Zhumin ^{[1
]}

机构：

[1] Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China

[2] Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2018年 / 120卷

关键词：

HLM; KYLIN-II; Double wall tube; Powder gap; Non-uniform flow; Thermal resistance; DEVELOPMENT STRATEGY; NACIE FACILITY; DESIGN; CONDUCTIVITY; SIMULATIONS; PROGRESS; REACTOR;

D O I：

10.1016/j.anucene.2018.06.016

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Non-contacted double-walled-straight-tube heat exchanger has been designed for the Lead-Bismuth Eutectic (LBE) loop KYLIN-II, the flow rate and temperature distribution dramatically influence the performance of heat exchanger. The Computational Fluid Dynamics (CFD) and numerical heat transfer method has been used to build the three-dimensional model of the heat exchanger. Adopting the SST (Shear Stress Transport) k-omega model the flow rate and temperature distribution of the heat exchanger model has been calculated. The numerical simulation result shows that the non-uniform LBE flows don't affect TH performance of HX filled with powder in the gap between two tubes. (C) 2018 Elsevier Ltd. All rights reserved.

引用

页码：604 / 610

页数：7

共 20 条

[1]

Dwyer O. E, 1970, NA NAK HDB

[2] Recent progress of R&D activities on reduced activation ferritic/martensitic steels [J].

Huang, Q. ;

Baluc, N. ;

Dai, Y. ;

Jitsukawa, S. ;

Kimura, A. ;

Konys, J. ;

Kurtz, R. J. ;

Lindau, R. ;

Muroga, T. ;

Odette, G. R. ;

Raj, B. ;

Stoller, R. E. ;

Tan, L. ;

Tanigawa, H. ;

Tavassoli, A. -A. F. ;

Yamamoto, T. ;

Wan, F. ;

Wu, Y. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) :S2-S8

[3] Thermal Conductivity of Diamond Composites [J].

Kidalov, Sergey V. ;

Shakhov, Fedor M. .

MATERIALS, 2009, 2 (04) :2467-2495

[4] Preliminary validation of RELAP5/Mod4.0 code for LBE cooled NACIE facility [J].

Kumari, Indu ;

Khanna, Ashok .

NUCLEAR ENGINEERING AND DESIGN, 2017, 314 :217-226

[5] Pre-test CFD simulations of the NACIE-UP BFPS test section [J].

Marinari, R. ;

Di Piazza, I. ;

Forgione, N. ;

Magugliani, F. .

ANNALS OF NUCLEAR ENERGY, 2017, 110 :1060-1072

[6] CFD thermo-hydraulic analysis of the CIRCE fuel bundle [J].

Martelli, Daniele ;

Marinari, Ranieri ;

Barone, Gianluca ;

di Piazza, Ivan ;

Tarantino, Mariano .

ANNALS OF NUCLEAR ENERGY, 2017, 103 :294-305

[7] Coupled simulations of the NACIE facility using RELAP5 and ANSYS FLUENT codes [J].

Martelli, Daniele ;

Forgione, Nicola ;

Barone, Gianluca ;

di Piazza, Ivan .

ANNALS OF NUCLEAR ENERGY, 2017, 101 :408-418

[8]

OECD-NEA, 2007, Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies

[9] Experimental investigation on powder conductivity for the application to double wall heat exchanger (NACIE-UP) [J].

Rozzia, Davide ;

Fasano, Giuseppe ;

Di Piazza, Ivan ;

Tarantino, Mariano .

NUCLEAR ENGINEERING AND DESIGN, 2015, 283 :100-113

[10]

Rozzia Davide, 2012, ICNENE2012

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