A Stabilizing Numerical Scheme of the CUPID for a Fast Transient Two Phase Flow
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Pusan National University, Busan (Korea, Republic of)
Description
A high resolution thermal-hydraulic code, CUPID, has been developed at KAERI for the application to a component-scale analysis of the reactor coolant system. Two-fluid three-field governing equations are discretized using an unstructured finite volume method (FVM). The solution algorithm is based on the semi-implicit method, where the momentum equation is solved explicitly and the pressure is calculated using the scalar equations. In this paper, a fast and robust solution algorithm of CUPID is presented for the calculation of a fast transient two phase flow where the interfacial heat transfer coefficient changes sharply. The numerical scheme was verified by a calculation of a two dimensional conceptual problem of a blowdown and refill event
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2011 spring meeting of the KNS
- Dates
- 26-27 May 2011
- Place
- Taebaek (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42099218
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALGORITHMS; BLOWDOWN; COMPUTER CALCULATIONS; EQUATIONS; HEAT TRANSFER; REACTOR COOLING SYSTEMS; THERMAL HYDRAULICS; TRANSIENTS; TWO-PHASE FLOW
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MATHEMATICAL LOGIC; MECHANICS; REACTOR COMPONENTS
Optional Information
- Notes
- 3 refs, 3 figs