Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method

Research output: Contribution to journalArticlepeer-review

20 Scopus citations

Abstract

The SACOS code is thermal-hydraulic subchannel analysis code designed to meet steady-state conditions and operational transients in different types of reactor cores. It uses a homogeneous flow or drift-flux model to simulate single-phase and two-phase flow characteristics. In order to achieve a more refined two-phase flow modeling for LWR cores, a new eight-equation two-fluid based analysis module of SACOS is developed in this study. The phasic equations for mass continuity, momentum, and energy are spatially discretized by the finite volume method (FVM) with a staggered grid structure. To reduce numerical diffusion and improve numerical accuracy, the high-resolution scheme with nonlinear flux limiter is implemented. The code assessment is performed with linear advection flow problem and the preliminary code validation is presented by comparing with the experimental results of Weiss 14 × 14 blockage test, CNEN 4 × 4 mixing test, Studsvik 3 × 3 mixing test, and ISPRA 4 × 4 mixing test covering single/two-phase and unheated/heated conditions. The application of SACOS implies that the code can be used to model and perform assembly-level core safety analysis with visualization capabilities for hexagonal and rectangular geometry.

Original languageEnglish
Article number103671
JournalProgress in Nuclear Energy
Volume134
DOIs
StatePublished - Apr 2021

Keywords

  • High-resolution scheme
  • Preliminary assessment and validation
  • Reactor core thermal-hydraulics
  • SACOS
  • Two-fluid model

Fingerprint

Dive into the research topics of 'Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method'. Together they form a unique fingerprint.

Cite this