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SCDAP/RELAP5-3D©
An Advanced Computer Code for Reactor Accident Analysis
SCDAP/RELAP5-3D© is the latest in a series of software packages developed at the Idaho National Laboratory (INL) for the analysis of severe accidents in water-cooled nuclear power plants and related systems. SCDAP-3D/RELAP5© is the result of merging severe accident analysis models developed for both the U.S. NRC and DOE reactor safety analysis programs with the state-of-the-art thermal/hydraulic analysis package, RELAP5-3D©. The code is capable of modeling a wide range of system configurations from single pipes, to experimental facilities, to full-scale reactor systems. The system of interest can be modeled with an arbitrary number of hydrodynamic volumes, structural and core components and is capable of describing the changes in geometry associated with damage in the core. The calculations of damage progression include meltdown of fuel rods and structures, fragmentation of embrittled fuel rods, convective and radiative heat transfer in porous debris, formation of a molten pool of core material, and the slumping of material to the lower head.
A two dimensional, finite element heat conduction model based on the COUPLE code may be used to calculate the heatup of the lower head of the reactor vessel and the slumped material support by the lower head. The most important use of this is to calculate theheatup and failure of the vessel lower head.
SCDAP-3D News
- The agenda for the 2003 RELAP5 International Users Seminar has been posted. The seminar will take place August 27-29, in West Yellowstone, Montana.
Availability
SCDAP/RELAP5-3D© is available from the INL through
membership in the International RELAP5 Users Group (IRUG).
Questions or problems regarding this web site should be directed to
webmaster@inl.gov.
Last modified: July 7, 2004.