Experimental investigation and correlation development for liquid carryover during reflood

被引：2

作者：

Beck, Faith R. ^{[1
,4
]}

Garrett, Grant R. ^{[1
,2
,5
]}

Mishra, Partha P. ^{[1
]}

Cheung, Fan-Bill ^{[1
,2
]}

Bajorek, Stephen M. ^{[3
]}

Hoxie, Chris L. ^{[3
]}

Tien, Kirk ^{[3
]}

机构：

[1] Penn State Univ, Dept Mech Engn, University Pk, PA 16802 USA

[2] Penn State Univ, Dept Nucl Engn, University Pk, PA 16802 USA

[3] US Nucl Regulatory Commiss, Off Nucl Regulatory Res, Washington, DC 20555 USA

[4] GE Global Res, Niskayuna, NY 12309 USA

[5] Raytheon Intelligence & Space, El Segundo, CA 90245 USA

来源：

NUCLEAR ENGINEERING AND DESIGN | 2023年 / 412卷

关键词：

Liquid carryover; Entrainment; Reflood; LOCA; Oscillatory flow; QUENCH FRONT; DROPLET; INJECTION; STEADY;

D O I：

10.1016/j.nucengdes.2023.112440

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：

A correlation is developed for the liquid carryover fraction during both constant and oscillatory reflood with application to nuclear power accidents. The correlation, semi-empirical in nature, is based on extensive experiments in a 7 x 7 rod bundle array at the Nuclear Regulatory Commission/Pennsylvania State University Rod Bundle Heat Transfer (NRC/PSU RBHT) facility. Liquid carryover and entrainment can significantly impact quench behavior and maximum cladding temperatures during a postulated accident; therefore, accurate predictions of these phenomena are critical. The parameters associated with the stability at the liquid-vapor interface, and hence the liquid entrainment and subsequent carryover are established. These parameters provide the basic form of the correlation with experimental data from the NRC/PSU RBHT facility to determine the model coefficients. Using a weighted least-squares method that minimizes the error between modeled and experimental carryover fraction, we implemented a genetic algorithm to identify the parameters of this correlation. The proposed model is compared with experimental data and predictions from the NRC's TRACE code and lies within 20% error margin.

引用

页数：9

共 29 条

[1]

Bajorek S., 2008, TRACE V5. 0 Theory manual, field equations, solution methods and physical models

[2]

Beck F.R., 2019, Experimental and Theoretical Study of Oscillatory Two-Phase Flows with Heat and Mass Transfer

[3] An engineering stability technique for unsteady, two-phase flows with heat and mass transfer [J].

Beck, Faith R. ;

Mohanta, Lokanath ;

Henderson, Diane M. ;

Cheung, Fan-Bill ;

Talmage, Gita .

INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2021, 142

[4]

Beck Faith R., 2016, INT TOPICAL M ADV TH

[5]

Beck Faith R., 2018, EMBEDDED TOPICAL INT

[6]

Bestion D., 2004, Recent advances in thermal hydraulics modeling for the CATHARE code

[7]

Blaisdell J., 1973, PWR FLECHT-SET phase A report

[8] Reflooding model for quasi-intact rod configuration: Quench front tracking and heat transfer closure laws [J].

Chikhi, Nourdine ;

Fichot, Florian .

NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) :3387-3396

[9]

Garrett Garrett, 2020, ATH 2020

[10]

Garrett Garrett, 2022, 19 INT TOPICAL M NUC

← 1 2 3 →