Published 2009 | Version v1
Miscellaneous

An improved semi-implicit numerical scheme for transient three-dimensional two-phase flow analysis

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 2. Thermal Hydraulics and Nuclear Safety Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 3. Department of Aerospace Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

Description

KAERI has developed the CUPID-I code for the analysis of transient two-phase flows in light water nuclear reactor components. In the CUPID-I code, a two-fluid three-field model is used and the governing equations are solved on unstructured grids. For the numerical solution scheme, the existing semi-implicit method of the RELAP5 code was used with some modifications for an application to non-staggered unstructured grids. This paper presents the recent improvements of the CUPID-I numerical scheme. In the previous scheme, the mass and energy equations were coupled with the momentum equations to obtain the pressure equation. The resulting pressure equation was an asymmetric matrix, which requires a long computation time. In the modified scheme, only the mass equations are implicitly coupled with the momentum equations and the energy equations are explicitly coupled. These modifications lead to a symmetric pressure equation, resulting in a fast running feature. In addition, a second-order upwind scheme was implemented for convection terms. The Green-Gauss reconstruction method suggested by Frink was modified for unstructured grids and the slope limiter by Barth and Jesperson were adapted in the CUPID-I code. To verify the numerical improvements, conceptual problems with a variety of two-phase flow conditions are solved. (author)

Part of:
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Imprint Title
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[4617 p.]
Journal Page Range
[19 p.]

Conference

Title
13. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-13
Dates
27 Sep - 2 Oct 2009
Place
Kanazawa, Ishikawa (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
43036713
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BOILING; C CODES; FLASHING; FLOW MODELS; GAS FLOW; LIQUID FLOW; NUMERICAL SOLUTION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; VOID FRACTION; VOIDS; WATER COOLED REACTORS
Descriptors DEC
COMPUTER CODES; EVAPORATION; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL MODELS; MATHEMATICAL SOLUTIONS; MECHANICS; PHASE TRANSFORMATIONS; REACTORS

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1231.pdf