Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en

Tian Yonghong; Tian Wenxi; Meng Zhaoming; Yingwei Wu; Guanghui Su; Suizheng Qiu

doi:10.1115/ICONE22-30881

Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en

Tian Yonghong
, Tian Wenxi
, Meng Zhaoming
, Yingwei Wu
, Guanghui Su
, Suizheng Qiu

School of Energy and Power Engineering

Xi'an Jiaotong University

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

2 Scopus citations

Abstract

Lead-bismuth eutectic(LBE) cooled fast reactor, one of the six types of reactors in Gen-IV, has very good inherent safety and significant advantages in reducing and burning nuclear wastes, enhancing economy. Also LBE cooled accelerator driven system (ADS) has been a very innovative and potential waste burner. COBRA-EN is a mature, stable and widely-used sub-channel analysis code for light water cooled reactor but it couldn't be applied in Pb-Bi-cooled reactor directly. Some modifications were made for COBRA-EN in the present work, then the code was named COBRA-PB and was suitable for the sub-channel analysis of Pb-Bi-cooled reactor. The modified code was verified and validated with CFX and experimental results. There was a good agreement between the two results. Then sub-channel analysis of Pb-Bi-cooled reactor was done with the modified code..

Original language	English
Title of host publication	Thermal Hydraulics
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791845912
DOIs	https://doi.org/10.1115/ICONE22-30881
State	Published - 2014
Event	2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic Duration: 7 Jul 2014 → 11 Jul 2014

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	2B

Conference

Conference	2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Country/Territory	Czech Republic
City	Prague
Period	7/07/14 → 11/07/14

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10.1115/ICONE22-30881

Cite this

@inproceedings{e11437b843db4573bfe1db90c0839a3b,

title = "Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en",

abstract = "Lead-bismuth eutectic(LBE) cooled fast reactor, one of the six types of reactors in Gen-IV, has very good inherent safety and significant advantages in reducing and burning nuclear wastes, enhancing economy. Also LBE cooled accelerator driven system (ADS) has been a very innovative and potential waste burner. COBRA-EN is a mature, stable and widely-used sub-channel analysis code for light water cooled reactor but it couldn't be applied in Pb-Bi-cooled reactor directly. Some modifications were made for COBRA-EN in the present work, then the code was named COBRA-PB and was suitable for the sub-channel analysis of Pb-Bi-cooled reactor. The modified code was verified and validated with CFX and experimental results. There was a good agreement between the two results. Then sub-channel analysis of Pb-Bi-cooled reactor was done with the modified code..",

author = "Tian Yonghong and Tian Wenxi and Meng Zhaoming and Yingwei Wu and Guanghui Su and Suizheng Qiu",

note = "Publisher Copyright: Copyright {\textcopyright} 2014 by ASME.; 2014 22nd International Conference on Nuclear Engineering, ICONE 2014 ; Conference date: 07-07-2014 Through 11-07-2014",

year = "2014",

doi = "10.1115/ICONE22-30881",

language = "英语",

series = "International Conference on Nuclear Engineering, Proceedings, ICONE",

publisher = "American Society of Mechanical Engineers (ASME)",

booktitle = "Thermal Hydraulics",

}

Yonghong, T, Wenxi, T, Zhaoming, M, Wu, Y , Su, G & Qiu, S 2014, Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en. in Thermal Hydraulics. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 2B, American Society of Mechanical Engineers (ASME), 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, Prague, Czech Republic, 7/07/14. https://doi.org/10.1115/ICONE22-30881

Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en. / Yonghong, Tian; Wenxi, Tian; Zhaoming, Meng et al.
Thermal Hydraulics. American Society of Mechanical Engineers (ASME), 2014. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2B).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en

AU - Yonghong, Tian

AU - Wenxi, Tian

AU - Zhaoming, Meng

AU - Wu, Yingwei

AU - Su, Guanghui

AU - Qiu, Suizheng

PY - 2014

Y1 - 2014

N2 - Lead-bismuth eutectic(LBE) cooled fast reactor, one of the six types of reactors in Gen-IV, has very good inherent safety and significant advantages in reducing and burning nuclear wastes, enhancing economy. Also LBE cooled accelerator driven system (ADS) has been a very innovative and potential waste burner. COBRA-EN is a mature, stable and widely-used sub-channel analysis code for light water cooled reactor but it couldn't be applied in Pb-Bi-cooled reactor directly. Some modifications were made for COBRA-EN in the present work, then the code was named COBRA-PB and was suitable for the sub-channel analysis of Pb-Bi-cooled reactor. The modified code was verified and validated with CFX and experimental results. There was a good agreement between the two results. Then sub-channel analysis of Pb-Bi-cooled reactor was done with the modified code..

AB - Lead-bismuth eutectic(LBE) cooled fast reactor, one of the six types of reactors in Gen-IV, has very good inherent safety and significant advantages in reducing and burning nuclear wastes, enhancing economy. Also LBE cooled accelerator driven system (ADS) has been a very innovative and potential waste burner. COBRA-EN is a mature, stable and widely-used sub-channel analysis code for light water cooled reactor but it couldn't be applied in Pb-Bi-cooled reactor directly. Some modifications were made for COBRA-EN in the present work, then the code was named COBRA-PB and was suitable for the sub-channel analysis of Pb-Bi-cooled reactor. The modified code was verified and validated with CFX and experimental results. There was a good agreement between the two results. Then sub-channel analysis of Pb-Bi-cooled reactor was done with the modified code..

UR - https://www.scopus.com/pages/publications/84911438122

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DO - 10.1115/ICONE22-30881

M3 - 会议稿件

AN - SCOPUS:84911438122

T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

BT - Thermal Hydraulics

PB - American Society of Mechanical Engineers (ASME)

T2 - 2014 22nd International Conference on Nuclear Engineering, ICONE 2014

Y2 - 7 July 2014 through 11 July 2014

ER -

Sub-channel analysis of pb-bi-cooled reactor with modified cobra-en

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