Recommendations on two-phase critical non-flashing flows calculations in one-dimensional system code RELAP5

Lukasz Sokolowski, Tomasz Kozlowski

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

Abstract

Two-phase critical non-flashing flow might occur, e.g. when a system filled with water and non- condensable gas as air or nitrogen, is emergency released. The common practice in Swedish industry is to employ one-dimensional system codes such as RELAP5 to calculate this type of flow. Such codes have in-build two-phase critical flow models which are intended for flashing steam-water mixture. However, non-flashing flows are different in its nature than flashing flows and because of this the default models might provide non-physical results. This paper aims to validate these models against experimental data and provide recommendations on how to predict non-flashing flows with satisfactory accuracy. Validation was performed against experimental data of [1] - [3] with water stagnation pressure conditions varying from 0.1 to 1.56 MPa, temperature subcooling in the range of 84.7 - 195.6 °C, maximum air mass flux of 383.2 kg/(m2 sec) and discharge section geometry arranged as an open pipe outlet, converging-diverging nozzle and converging nozzle.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages2117-2130
Number of pages14
ISBN (Electronic)9781510811843
StatePublished - Jan 1 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume3

Other

Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/TerritoryUnited States
CityChicago
Period8/30/159/4/15

Keywords

  • Non-flashing mixtures
  • Nuclear safety analysis
  • Two-phase critical flow

ASJC Scopus subject areas

  • Instrumentation
  • Nuclear Energy and Engineering

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