Closed-loop experimental investigation of single-phase natural circulation flow phenomena based on temperature and heating power variations

被引：4

作者：

Bello, Solomon ^{[1
]}

Gao, Puzhen ^{[1
]}

Lin, Yuqi ^{[1
]}

机构：

[1] Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin 150001, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2021年 / 151卷

关键词：

Natural circulation; Single-phase flow; Temperature variation; Power variation; Closed-loop; Heat transfer;

D O I：

10.1016/j.anucene.2020.107809

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：

Experimental investigation of single-phase, low pressure natural circulation flow phenomena has been carried out. The study aims to critically analyze the thermal hydraulic parameters (temperature and heating power) variations as it affects transfer of heat in a closed-loop rectangular natura l circulation facility having a single heated channel at predetermined inlet sub cooled temperature varied from 40 to 80 degrees C. Heating power varies between 7 kW-13 kW to portray several conditions of the reactor power in response to temperature changes while sustaining single-phase flow circulation through the hydraulic loop. Real-time signals of thermal hydraulic responses are observed via a graphical interface for data acquisition when stable flow or self-sustained flow oscillations are achieved. Results obtained were analyzed at several sections of the hydraulic circuit which are basically pressure drops and flow rate due to temperature differences and heating power increments. These results and observations made through them thus contribute to the database which is important for characterizing natural circulation phenomena and acquisition of dominants parameters for the scaling analysis of future designs. (C) 2020 Elsevier Ltd. All rights reserved.

引用

页数：10

共 13 条

[1] A review of modern advances in analyses and applications of single-phase natural circulation loop in nuclear thermal hydraulics [J].

Basu, Dipankar N. ;

Bhattacharyya, Souvik ;

Das, P. K. .

NUCLEAR ENGINEERING AND DESIGN, 2014, 280 :326-348

[2]

Bello S., E ES 2020 IOPSCIENCE

[3] An experimental investigation of flow boiling instability in a natural circulation loop [J].

Chen, Xianbing ;

Gao, Puzhen ;

Tan, Sichao ;

Yu, Zhiting ;

Chen, Chong .

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2018, 117 :1125-1134

[4] Experimental investigation on the flow instability behavior of a multi-channel boiling natural circulation loop at low-pressures [J].

Jain, Vikas ;

Nayak, A. K. ;

Vijayan, P. K. ;

Saha, D. ;

Sinha, R. K. .

EXPERIMENTAL THERMAL AND FLUID SCIENCE, 2010, 34 (06) :776-787

[5]

Juarsa M., 2018, IOP C SERIES EARTH E

[6] Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility [J].

Kozmenkov, Y. ;

Rohde, U. ;

Manera, A. .

NUCLEAR ENGINEERING AND DESIGN, 2012, 243 :168-175

[7] Capability of the RELAP5 code to simulate natural circulation behavior in test facilities [J].

Mangal, Amit ;

Jain, Vikas ;

Nayak, A. K. .

PROGRESS IN NUCLEAR ENERGY, 2012, 61 :1-16

[8] Contribution of thermal-hydraulic validation tests to the standard design approval of SMART [J].

Park, Hyun-Sik ;

Kwon, Tae-Soon ;

Moon, Sang-Ki ;

Cho, Seok ;

Euh, Dong-Jin ;

Yi, Sung-Jae .

NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (07) :1537-1546

[9]

Pritchard PJ., 2016, Fox and McDonald's introduction to fluid mechanics

[10] Comparison Between Experimental Data and Numerical Modeling for the Natural Circulation Phenomenon [J].

Sabundjian, Gaiane ;

de Andrade, Delvonei A. ;

Umbehaun, Pedro E. ;

Torres, Walmir M. ;

Macedo, Luiz A. ;

Conti, Thadeu N. ;

de Mesquita, Roberto N. ;

Angelo, Gabriel .

JOURNAL OF THE BRAZILIAN SOCIETY OF MECHANICAL SCIENCES AND ENGINEERING, 2011, 33 :227-232

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