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Inconsistency in the average hydraulic models used in nuclear reactor design and safety analysis

Abstract

One of important inconsistencies in the six-equation model predictions has been found to be the force experienced by a single bubble placed in a convergent stream of liquid. Various sets of governing equations yield different amount of forces to hold the bubble stationary in a convergent nozzle. By using the first order potential flow theory, it is found that the six-equation model can not be used to estimate the force experienced by a deformed bubble. The theoretical value of the particle stress of a bubble in a convergent nozzle flow has been found to be a function of the Weber number when bubble distortion is allowed. This force has been calculated by using different sets of governing equations and compared with the theoretical value. It is suggested in this study that the bubble size distribution function can be used to remove the presented inconsistency by relating the interfacial variables with different moments of the bubble size distribution function. This study also shows that the inconsistencies in the thermal-hydraulic governing equation can be removed by mechanistic modeling of the phasic interface. 11 refs., 3 figs. (Author)
Authors:
Park, Jee Won; Roh, Gyu Hong; Choi, Hang Bok [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Dec 31, 1997
Product Type:
Conference
Report Number:
ETDE/KR-99732628; CONF-9710296-
Reference Number:
SCA: 420400; PA: KR-99:000317; EDB-99:037402; SN: 99002059944
Resource Relation:
Conference: Korean Nuclear Society autumn meeting, Taegu (Korea, Republic of), 24-25 Oct 1997; Other Information: PBD: 1997; Related Information: Is Part Of Proceedings of the korean nuclear society autumn meeting vol I, October 24-25, 1997 Taegu, Korea; PB: 797 p.
Subject:
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; HYDRAULICS; SAFETY; REACTOR SAFETY; BUBBLE CHAMBERS; POTENTIAL FLOW; FLUID FLOW; NOZZLES; BUBBLE GROWTH; BUBBLES; DISTRIBUTION FUNCTIONS; SIZE
OSTI ID:
324162
Research Organizations:
Korean Nuclear Society, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE99732628; TRN: KR9900317
Availability:
OSTI as DE99732628
Submitting Site:
KR
Size:
pp. 599-604
Announcement Date:
Apr 01, 1999

Citation Formats

Park, Jee Won, Roh, Gyu Hong, and Choi, Hang Bok. Inconsistency in the average hydraulic models used in nuclear reactor design and safety analysis. Korea, Republic of: N. p., 1997. Web.
Park, Jee Won, Roh, Gyu Hong, & Choi, Hang Bok. Inconsistency in the average hydraulic models used in nuclear reactor design and safety analysis. Korea, Republic of.
Park, Jee Won, Roh, Gyu Hong, and Choi, Hang Bok. 1997. "Inconsistency in the average hydraulic models used in nuclear reactor design and safety analysis." Korea, Republic of.
@misc{etde_324162,
title = {Inconsistency in the average hydraulic models used in nuclear reactor design and safety analysis}
author = {Park, Jee Won, Roh, Gyu Hong, and Choi, Hang Bok}
abstractNote = {One of important inconsistencies in the six-equation model predictions has been found to be the force experienced by a single bubble placed in a convergent stream of liquid. Various sets of governing equations yield different amount of forces to hold the bubble stationary in a convergent nozzle. By using the first order potential flow theory, it is found that the six-equation model can not be used to estimate the force experienced by a deformed bubble. The theoretical value of the particle stress of a bubble in a convergent nozzle flow has been found to be a function of the Weber number when bubble distortion is allowed. This force has been calculated by using different sets of governing equations and compared with the theoretical value. It is suggested in this study that the bubble size distribution function can be used to remove the presented inconsistency by relating the interfacial variables with different moments of the bubble size distribution function. This study also shows that the inconsistencies in the thermal-hydraulic governing equation can be removed by mechanistic modeling of the phasic interface. 11 refs., 3 figs. (Author)}
place = {Korea, Republic of}
year = {1997}
month = {Dec}
}