Current status of thermohydraulic validation studies at CEA-Grenoble for the SIMMER-III code
Creators
- 1. Commissariat a l'Energie Atomique (CEA), DRN/DTP/SMTH, Grenoble (France)
- 2. CISI Company (France)
Description
SIMMER-III (SIII) is a two-dimensional, three-velocity-field, multiphase, multicomponent, Eulerian, fluid-dynamics code coupled with a space- and energy-dependent neutron kinetics model, to investigate postulated core disruptive accidents in LMFRs. It is developed by PNC, Japan. The paper makes the synthesis of the SIII assessment performed at CEA-Grenoble since 1996, which covers a large variety of multiphase flows, from two-phase flow basic modelling to LMFR accident simulation experiments with real materials. Single bubbles or droplets equilibrium radii and velocities, air/water experiments in tubes, and comparisons with the literature, are used to qualify the interfacial area convection equation and the momentum exchange functions. Using the second order differencing scheme of the Navier-Stokes equation, a turbulence model for two-phase recirculating flows is implemented. It is successfully validated on an adiabatic air/water experiment, and on the Sebulon boiling pool simulation experiment, which is a box of water internally heated, with a cover gas, and cooled at the walls. The successful calculations of the SGI experiment and of a reactor scale case contribute to the code validation for LMFR expansion phase. Besides, the large scale UO2/sodium interactions of the Termos T1 experiment, and the UO2 boiling pool laterally cooled with sodium flow at the wall of the Scarabee BF2 experiment, is also studied with SIM Lastly, satisfying results are obtained with the calculation of the Scarabee APL3 slow pump run down without scram. It is shown that SIII is a state-of-the-art tool to simulate transient multiphase phenomena. The paper also discusses those areas, identified through these assessment calculations, which require further research and development. (author)
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31032868.pdf
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Additional details
Publishing Information
- Imprint Title
- LMFR core thermohydraulics: Status and prospects
- Imprint Pagination
- 443 p.
- Journal Page Range
- p. 71-84
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1157
Conference
- Title
- Technical committee meeting on methods and codes for calculations of thermohydraulic parameters for fuel, absorber pins and assemblies of LMFR's with traditional and burner cores
- Dates
- 27-31 Jul 1998
- Place
- Obninsk (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31032868
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CEA; FLUID MECHANICS; FUEL-COOLANT INTERACTIONS; LMFBR TYPE REACTORS; MULTIPHASE FLOW; NAVIER-STOKES EQUATIONS; REACTOR CORE DISRUPTION; S CODES; SCARABEE REACTOR; SIMULATION; SODIUM; TWO-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; VALIDATION
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; ELEMENTS; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FRENCH ORGANIZATIONS; LIQUID METAL COOLED REACTORS; MECHANICS; METALS; NATIONAL ORGANIZATIONS; PARTIAL DIFFERENTIAL EQUATIONS; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 40 refs, 11 figs