Published October 2012 | Version v1
Miscellaneous

Investigation of the heat exchanger bundle effect for the passive condensate cooling tank using the CUPID code

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

Description

The need for a multi dimensional analysis of transient thermal hydraulic phenomena in a component of a nuclear reactor is increasing with the advanced design features. Motivated by this, the development of a new thermal hydraulic analysis code, named CUPID, is in progress at KAERI (Korea Atomic Energy Research Institute). The simulation of the passive secondary cooling system, PAFS (Passive Auxiliary Feedwater System) has been considered as one of the practical applications of CUPID. In order to validate the two phase flow models of CUPID, the PASCAL test facility was simulated with a porous media model in our previous study. In the present study, the heat exchanger bundle effect on the natural circulation heat transfer was investigated using CUPID for the passive condensate cooling tank (PCCT) of the PAFS. The calculation results with the porous media model, such as the liquid temperature and velocity, were imposed as boundary conditions of the detailed flow simulation near the single heat exchanger tube of the PASCAL facility. Thereafter, the bundle effect was investigated by comparing the calculation result of the unit cell of the PAFS tube bundle and that of the single tube. This paper presents the two dimensional porous media analysis result for the PCCT of the PASCAL facility, two dimensional open media analysis result for a single heat exchanger tube, and two dimensional open media analysis result for the unit cell of the heat exchanger bundle

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 autumn meeting of the KNS
Dates
24-26 Oct 2012
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44062769
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; COMPUTER CALCULATIONS; COOLING; DESIGN; FEEDWATER; HEAT EXCHANGERS; REACTORS; TANKS; THERMAL HYDRAULICS
Descriptors DEC
COMPUTER CODES; CONTAINERS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; WATER

Optional Information

Notes
2 refs, 6 figs