Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop

L. V. Kefeng; Sheng Gao; Liuli Chen; Chenchong Yue; Mariano Tarantino; Qunying Huang; Yican Wu

Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop

L. V. Kefeng
, Sheng Gao
, Liuli Chen
, Chenchong Yue
, Mariano Tarantino
, Qunying Huang
, Yican Wu

School of Energy and Power Engineering

Chinese Academy of Sciences
Jiangsu Higher Education Institutions
Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile

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

Abstract

Pure lead and its alloys are foreseen to be used as coolant and/or spallation target in the advanced nuclear systems. To investigate the behavior of Lead Bismuth Eutectic (LBE) cooled nuclear systems, KYLIN-II Thermal-Hydraulic (KYLIN-II TH) mixed circulation test loop has been designed and built in HEFEI by FDS team. The loop is a multipurpose facility aimed to investigate natural circulation, forced circulation and gas enhanced circulation in HLM systems. In this context, experimental data and correlations for the design of nuclear systems cooled with heavy liquid metals will be gained. The work concerns the preliminary tests performed on KYLIN-II TH. During the experiments, the facility was operated at 200-350 °C with heating power from 16 kW to 70 kW. The natural circulation, transient circulation and preliminary Loss of Flow Accident (LOFA) was carried out in this work. The experiments show that the steady state of natural circulation is easy to be established in a few minute. The time duration of temperature transition state, during the foundation of natural circulation in start-up of natural circulation test and LOFA in this work, is less than 300 s, however, depended on the operation parameters of the facility.

Original language	English
Title of host publication	International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Publisher	American Nuclear Society
Pages	7426-7433
Number of pages	8
ISBN (Electronic)	9781510811843
State	Published - 2015
Event	16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States Duration: 30 Aug 2015 → 4 Sep 2015

Publication series

Name	International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume	9

Conference

Conference	16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/Territory	United States
City	Chicago
Period	30/08/15 → 4/09/15

Keywords

Lead-bismuth eutectic coolant
LOFA transient
Natural circulation

Cite this

Kefeng, L. V., Gao, S., Chen, L., Yue, C., Tarantino, M., Huang, Q., & Wu, Y. (2015). Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (pp. 7426-7433). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 9). American Nuclear Society.

Kefeng, L. V. ; Gao, Sheng ; Chen, Liuli et al. / Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. pp. 7426-7433 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).

@inproceedings{3a6f3787f26a4615aaff297245c0b78f,

title = "Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop",

abstract = "Pure lead and its alloys are foreseen to be used as coolant and/or spallation target in the advanced nuclear systems. To investigate the behavior of Lead Bismuth Eutectic (LBE) cooled nuclear systems, KYLIN-II Thermal-Hydraulic (KYLIN-II TH) mixed circulation test loop has been designed and built in HEFEI by FDS team. The loop is a multipurpose facility aimed to investigate natural circulation, forced circulation and gas enhanced circulation in HLM systems. In this context, experimental data and correlations for the design of nuclear systems cooled with heavy liquid metals will be gained. The work concerns the preliminary tests performed on KYLIN-II TH. During the experiments, the facility was operated at 200-350 °C with heating power from 16 kW to 70 kW. The natural circulation, transient circulation and preliminary Loss of Flow Accident (LOFA) was carried out in this work. The experiments show that the steady state of natural circulation is easy to be established in a few minute. The time duration of temperature transition state, during the foundation of natural circulation in start-up of natural circulation test and LOFA in this work, is less than 300 s, however, depended on the operation parameters of the facility.",

keywords = "Lead-bismuth eutectic coolant, LOFA transient, Natural circulation",

author = "Kefeng, \{L. V.\} and Sheng Gao and Liuli Chen and Chenchong Yue and Mariano Tarantino and Qunying Huang and Yican Wu",

year = "2015",

language = "英语",

series = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",

publisher = "American Nuclear Society",

pages = "7426--7433",

booktitle = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",

note = "16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 ; Conference date: 30-08-2015 Through 04-09-2015",

}

Kefeng, LV, Gao, S, Chen, L, Yue, C, Tarantino, M, Huang, Q & Wu, Y 2015, Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop. in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, vol. 9, American Nuclear Society, pp. 7426-7433, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 30/08/15.

Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop. / Kefeng, L. V.; Gao, Sheng; Chen, Liuli et al.
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 2015. p. 7426-7433 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 9).

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

TY - GEN

T1 - Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop

AU - Kefeng, L. V.

AU - Gao, Sheng

AU - Chen, Liuli

AU - Yue, Chenchong

AU - Tarantino, Mariano

AU - Huang, Qunying

AU - Wu, Yican

PY - 2015

Y1 - 2015

N2 - Pure lead and its alloys are foreseen to be used as coolant and/or spallation target in the advanced nuclear systems. To investigate the behavior of Lead Bismuth Eutectic (LBE) cooled nuclear systems, KYLIN-II Thermal-Hydraulic (KYLIN-II TH) mixed circulation test loop has been designed and built in HEFEI by FDS team. The loop is a multipurpose facility aimed to investigate natural circulation, forced circulation and gas enhanced circulation in HLM systems. In this context, experimental data and correlations for the design of nuclear systems cooled with heavy liquid metals will be gained. The work concerns the preliminary tests performed on KYLIN-II TH. During the experiments, the facility was operated at 200-350 °C with heating power from 16 kW to 70 kW. The natural circulation, transient circulation and preliminary Loss of Flow Accident (LOFA) was carried out in this work. The experiments show that the steady state of natural circulation is easy to be established in a few minute. The time duration of temperature transition state, during the foundation of natural circulation in start-up of natural circulation test and LOFA in this work, is less than 300 s, however, depended on the operation parameters of the facility.

AB - Pure lead and its alloys are foreseen to be used as coolant and/or spallation target in the advanced nuclear systems. To investigate the behavior of Lead Bismuth Eutectic (LBE) cooled nuclear systems, KYLIN-II Thermal-Hydraulic (KYLIN-II TH) mixed circulation test loop has been designed and built in HEFEI by FDS team. The loop is a multipurpose facility aimed to investigate natural circulation, forced circulation and gas enhanced circulation in HLM systems. In this context, experimental data and correlations for the design of nuclear systems cooled with heavy liquid metals will be gained. The work concerns the preliminary tests performed on KYLIN-II TH. During the experiments, the facility was operated at 200-350 °C with heating power from 16 kW to 70 kW. The natural circulation, transient circulation and preliminary Loss of Flow Accident (LOFA) was carried out in this work. The experiments show that the steady state of natural circulation is easy to be established in a few minute. The time duration of temperature transition state, during the foundation of natural circulation in start-up of natural circulation test and LOFA in this work, is less than 300 s, however, depended on the operation parameters of the facility.

KW - Lead-bismuth eutectic coolant

KW - LOFA transient

KW - Natural circulation

UR - https://www.scopus.com/pages/publications/84964059154

M3 - 会议稿件

AN - SCOPUS:84964059154

T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

SP - 7426

EP - 7433

BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

PB - American Nuclear Society

T2 - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015

Y2 - 30 August 2015 through 4 September 2015

ER -

Kefeng LV, Gao S, Chen L, Yue C, Tarantino M, Huang Q et al. Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society. 2015. p. 7426-7433. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).

Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop

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