0
Technical Brief

Numerical Analysis of Sub-Cooled Water Flashing Flow from a Pressurized Water Reactor Steam Generator through an Abruptly Broken Main Feed Water Pipe

[+] Author and Article Information
Jong Chull Jo

Pusan National University, School of Mechanical Engineering, 63 Busandaehak-ro, Geumjeong-gu, Busan, 46241, Korea; Korea Institute of Nuclear Safety, Reactor System Evaluation Dept., 62 Gwahak-ro, Yusung-gu, Daejon, 34142, Korea
jongcjo@pusan.ac.kr; jcjo@kins.re.kr

Jae Jun Jeong

Pusan National University, School of Mechanical Engineering, 63 Busandaehak-ro, Geumjeong-gu, Busan, 46241, Korea
jjjeong@pusan.ac.kr

Byongjo Yun

Pusan National University, School of Mechanical Engineering, 63 Busandaehak-ro, Geumjeong-gu, Busan, 46241, Korea
bjyun@pusan.ac.kr

Jongkap Kim

Pusan National University, School of Mechanical Engineering, 63 Busandaehak-ro, Geumjeong-gu, Busan, 46241, Korea
k233kjk@kins.re.kr

1Corresponding author.

ASME doi:10.1115/1.4043297 History: Received August 17, 2018; Revised March 17, 2019

Abstract

A computational fluid dynamics (CFD) analysis was performed to investigate the hydraulic response of the flow field inside the pressurized water reactor (PWR) steam generator (SG) secondary side and the connected part of main feed water pipe to an abrupt main feed water line break (FWLB) accident. To realistically analyze the transient flow field situation, the flow field was assumed to be occupied initially by highly compressed sub-cooled water except that the upper part of the SG secondary side where steam occupied as in the practical case and the break was assumed to occur at the circumferential weld line between the feed water nozzle and the main feed water pipe. This would result in a sub-cooled water flashing flow from the SG through the short broken pipe end to the surrounding atmosphere, which was numerically simulated in this study. Typical results of the prediction in terms of the fluid transient velocity and pressure were illustrated and discussed. To examine the physical validity of the present numerical simulation of the sub-cooled water flashing flow, the transient mass flow rates predicted in this study were compared with other previous numerical predictions based on the sub-cooled water non-flashing (no phase change) flow or saturated water flashing flow assumptions and the prediction by a simple analysis method.

Copyright (c) 2019 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Tables

Errata

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In