Simulation of Oscillatory Flow Induced by Flashing Instability Using the ASYST System Analysis Code

Taiyang Zhang, Caleb S. Brooks

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

Two-phase flow instabilities can lead to continuously evolving long-term behaviors involving various non-negligible phenomena. Prediction of instability consequences is therefore a challenge which requires comprehensive and robust models capturing critical physics consistently beyond steady states. As thermal hydraulic codes for reactor system analysis are typically developed with anticipated capability covering a wide spectrum of reactor transients, validation of these code in capturing flow instability is of practical interest. The current work tests the performance of a code, the Adaptive System Thermal-hydraulics Version 3 (ASYST VER3), in reproducing periodic limit-cycle oscillations induced by flashing instability on a low-pressure natural circulation facility. With prescribed periodic boundary conditions, single-channel simulations are conducted to investigate the code capability in correctly modeling two-phase phenomena. Discrepancies between the simulation and experiment are checked, leading to further analysis of potential modeling defects. In general, this work presents the simulation practices and validation attempts of a thermal hydraulic code, ASYST, against a benchmark dataset composing of periodic flow oscillations from flashing instability.

Original languageEnglish (US)
Title of host publicationProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PublisherAmerican Nuclear Society
Pages5358-5370
Number of pages13
ISBN (Electronic)9780894487934
DOIs
StatePublished - 2023
Externally publishedYes
Event20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States
Duration: Aug 20 2023Aug 25 2023

Publication series

NameProceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/TerritoryUnited States
CityWashington
Period8/20/238/25/23

Keywords

  • ASYST
  • flashing instability
  • transient system analysis
  • two-phase flow

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Instrumentation

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