Published October 2008 | Version v1
Miscellaneous

An Implementation of Turbulence Models into the CUPID code

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

A component-scale thermal-hydraulics analysis module, CUPID has been being developed for a transient three-dimensional two-phase flow analysis of nuclear reactor components. CUPID is based on a two-fluid, three-field model, which is solved by using an unstructured finite volume method. At present, turbulence effects are not considered in the CUPID code. However, the turbulence model is not to be neglected in a liquid single phase flow or a subcooled boiling flow even though a turbulence could be less important in other flow regimes of two phase flows. In this paper, the implementations of turbulence models into CUPID are discussed

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
2008 autumn meeting of the KNS
Dates
30-31 Oct 2008
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40066654
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BOILING; C CODES; REACTOR COMPONENTS; THERMAL HYDRAULICS; TURBULENCE; TWO-PHASE FLOW
Descriptors DEC
COMPUTER CODES; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHASE TRANSFORMATIONS

Optional Information

Notes
4 refs, 2 figs