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
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