Published 2008 | Version v1
Book

Analysis of fuel-coolant interaction with SOKRAT/VAPEX code

  • 1. Electrogorsk Research and Engineering Center for Safety of Nuclear Power Plants (EREC), Moscow (Russian Federation)

Description

For a number of years, a stand-alone code VAPEX intended for the simulation of fuel-coolant interaction has been under development at EREC [1]. Recently, a new module VAPEX-M has been developed and implemented as a part of an integral code SOKRAT [2] aimed for analysis of severe accidents. In the VAPEX-M module, the Lagrangian approach is used for the molten corium. The module describes the main processes of heat and mass transfer (heat fluxes from the high-temperature melt into the liquid and vapour phases, hydrogen production rate due to the oxidation of zirconium and steel) and provides relevant data into the thermohydraulic code provided by SOKRAT. The results of verification studies carried out by the combined SOKRAT/VAPEX code are presented. Three experimental series reported in the literature were chosen for the verification calculations: MAGICO [3], QUEOS [4], and FARO [5]. These experiments allow different aspects of fuel-coolant interaction to be verified: drag correlations (MAGICO), evaporation rate (QUEOS), fuel fragmentation and interaction with the coolant in all complexity (FARO). (orig.)

Part of:
Annual meeting on nuclear technology 2008. Proceedings

Additional details

Additional titles

Original title (English)
Jahrestagung Kerntechnik 2008. Tagungsbericht

Publishing Information

Publisher
Inforum Verlag
Imprint Place
Bonn (Germany)
Imprint Title
Annual meeting on nuclear technology 2008. Proceedings
Imprint Pagination
886 p.
Journal Page Range
p. 204-207

Conference

Title
2008 annual meeting on nuclear technology
Original Conference Title
Jahrestagung Kerntechnik (JK) 2008
Dates
27-29 May 2008
Place
Hamburg (Germany)

Optional Information

Notes
Imprint:Jahrestagung Kerntechnik 2008. Tagungsbericht