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Capabilities Presentation: pps

FUELSIM: A Computer Code Package for Analysis of Oxide Fuel Rod Behavior. FUELSIM is a Fortran software package designed to provide a comprehensive capability to analyze fuel rod performance of nuclear fuel rods. That includes analyses of steady state operation of reactor fuel, transient analyses of accident conditions, and behavior of spent fuel rods in storage. The code uses publicly available FRAPCON-2 models developed by the US Nuclear Regulatory Commission with proprietary improvements to improve the usability and reliability of the code.

FUELSIM performs an analysis of fuel rod behavior by calculating the integrated effects of thermal, mechanical, and chemical fuel rod behavior. FuelSim models all significant phenomena of a fuel rod including: heat conduction through the fuel and cladding using a finite difference heat conduction model in the fuel; cladding elastic and plastic deformation and fuel-cladding mechanical interaction using either a rigid-pellet model, Fracas-I, or a deformable pellet model, Fracas-II; fission gas release using either the ANS 5.4 or Massih model; fuel rod internal gas pressure using the gas law; heat transfer between fuel and cladding using several models including an enhancement to the Ross and Stoute model; cladding oxidation; and heat transfer from the cladding through oxide and crud to the coolant. The code is self contained and includes all necessary material properties, water properties, and heat transfer correlations. Consistent materials properties of fuel rod materials including gases in the rod are provided by MATPRO with some enhancements to extend the code to high burn up levels

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FUELSIM Presentation: pps

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Overview Presentation: pps 
National Autonomous University of Mexico RELAP/SCDAPSIM-Based Plant Simulation and Training Applications to the Laguna Verde NPP Paper: pdf

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FPTRAN prsentation: pps

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CAPE-BWR Presentation: pps

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CAPE-PWR Presentation: pps

RELAP/SCDAPSIM, designed to predict the behavior of reactor systems during normal and accident conditions, is being developed at Innovative Systems Software (ISS) as part of the international SCDAP Development and Training Program (SDTP). RELAP/SCDAPSIM uses the publicly available SCDAP/RELAP5 models developed by the US Nuclear Regulatory Commission in combination with proprietary (a) advanced programming and numerical methods, (b) user options, and (c) models developed by ISS and other members of the SDTP.. The RELAP5 models calculate the overall RCS thermal hydraulic response, control system behavior, reactor kinetics, and the behavior of special reactor system components such as valves and pumps. The SCDAP models calculate the behavior of the core and vessel structures under normal and accident conditions. The SCDAP portion of the code includes user-selectable reactor component models for LWR fuel rods, Ag-In-Cd and B4C control rods, BWR control blade/channel boxes, and general core and vessel structures. The SCDAP portion of the code also includes models to treat the later stages of a severe accident including debris and molten pool formation, debris/vessel interactions, and the structural failure (creep rupture) of vessel structures. The latter models are automatically invoked by the code as the damage in the core and vessel progresses. The RELAP5 and SCDAP models of RELAP/SCDAPSIM have been validated for a wide range of accident conditions using a variety of experiments and plant data including TMI-2. RELAP/SCDAPSIM/MOD3.4, the latest production version that is available to the general user community, includes (a) new models for fission product transport and deposition, fuel assembly behavior, and in-vessel melt retention, and (b) advanced programming and numerical techniques. RELAP/SCDAPSIM/MOD4, our latest experimental version available only to SDTP members, is the first version of RELAP5 that has been completely rewritten to FORTRAN 90/95 standards. This version is much easier for SDTP model/code developers to modify and includes the latest models and user features developed by ISS and SDPT members.

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Capabilities Presentation: pps 
Practical Examples of the Analysis of Severe Accidents Presentation:pps 
An Assessment of RELAP/SCDAPSIM/MOD3.4 Using the Phebus FPT-2 Bundle Heating and Melting Experiment Paper: pdf 
Developing and validating severe accident management guidelines using SAMPSON-RELAP/SCDAPSIM/MOD3.4 Paper: pdf 
Validation of RELAP/SCDAPSIM/MOD3.4 For Research Reactor Applications Paper: pdf

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Capabilities Presentation: pps 
Developing and Validating Severe Accident Management Guidelines using SAMPSON-RELAP/SCDAPIM/MOD3.4 Paper: pdf 
Assessment of Water Injection as Severe Accident Management Using SAMPSON code Paper: pdf