Analysis of fuel-coolant interaction with SOKRAT/VAPEX code
Creators
- 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.)
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)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42016976
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLOW RATE; FUEL-COOLANT INTERACTIONS; HYDROGEN PRODUCTION; HYPOTHETICAL ACCIDENTS; MATHEMATICAL MODELS; PARTICLES; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; S CODES; SEDIMENTATION; TEST FACILITIES; THERMAL HYDRAULICS; TIME DEPENDENCE; V CODES; VERIFICATION; ZIRCONIUM OXIDES
- Descriptors DEC
- ACCIDENTS; CHALCOGENIDES; COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; OXIDES; OXYGEN COMPOUNDS; SAFETY; SIMULATION; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2008. Tagungsbericht