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Communication Dans Un Congrès Année : 2022

Horizontal stratification criteria of 8 system codes and direct confrontation to TPTF and Mantilla data

M. Lanfredini
  • Fonction : Auteur
D. Bestion
  • Fonction : Auteur
F. d'Auria
  • Fonction : Auteur
N. Aydemir
  • Fonction : Auteur
Philippe Fillion
P. Gaillard
  • Fonction : Auteur
J.J. Jeong
  • Fonction : Auteur
J. Kurki
  • Fonction : Auteur
J.H. Lee
  • Fonction : Auteur
P. Schoeffel
  • Fonction : Auteur
H. Sha
  • Fonction : Auteur
J.L. Vacher
  • Fonction : Auteur
G. Waddington
  • Fonction : Auteur

Résumé

The horizontal stratification occurrence in water-cooled nuclear reactor plays an important role in many transients by influencing the liquid mass repartition, the natural circulation and reflux condenser modes, and the break flowrate. The FONESYS network of system thermal-hydraulic (SYS-TH) code developers made a comparison of horizontal stratification criteria used in the following codes: APROS, ATHLET, CATHARE, MARS-KS, RELAP5, RELAP5-3D, SPACE and TRACE. All the codes use a Kelvin-Helmholtz instability limit to model the transition from stratified flow to slug flow and define a stratified domain, a non-stratified domain and a transition domain in between. However, there are rather big differences among code. All use various forms of modified Froude numbers with the same diameter dependence, but the pressure and void fraction dependence are different among the codes. Some of the codes have also a criterion for the transition from bubbly to stratified flow using either a limiting mass flux or a limiting liquid Kutateladze number. Here again big differences exist among the codes. A code adds another condition related to the CCFL limit. The various models are directly confronted -without using the codes- with TPTF steam-water data and Mantilla air-water data in a large range of pressures and with diameters of 8, 6, 4 and 2 inches. Some code models do not perform very well. The results are analyzed and discussed in detail. Some miss-predictions may be attributed to non-established flow regimes. Other errors may suggest bad void and/or pressure effects. The scalability of some model is questioned.
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Dates et versions

cea-04371870 , version 1 (04-01-2024)

Identifiants

  • HAL Id : cea-04371870 , version 1

Citer

M. Lanfredini, D. Bestion, F. d'Auria, N. Aydemir, Sofia Carnevali, et al.. Horizontal stratification criteria of 8 system codes and direct confrontation to TPTF and Mantilla data. The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Mar 2022, Bruxelles (Virtual), Belgium. pp.35791. ⟨cea-04371870⟩
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