Published October 1997 | Version v1
Miscellaneous

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

  • 1. KAERI, Taejon (Korea, Republic of)

Description

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 the inconsistencies in the thermal-hydraulic governing equation can be removed by mechanistic modeling of the phasic interface

Part of:
Proceedings of the Korean Nuclear Society autumn meeting Vol. 1

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society autumn meeting Vol.1
Imprint Pagination
797 p.
Journal Page Range
p. 599-604

Conference

Title
1997 autumn meeting of the Korean Nuclear Society
Dates
24-25 Oct 1997
Place
Taegu (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33056650
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BUBBLES; DESIGN; EQUATIONS; HYDRAULICS; NOZZLES; REACTORS; SAFETY ANALYSIS; THERMAL ANALYSIS; TWO-PHASE FLOW
Descriptors DEC
FLUID FLOW; FLUID MECHANICS; MECHANICS

Optional Information

Notes
11 refs, 3 figs