The RELAP5/MOD3.2 R/T engineering quality plant simulation code has been developed based on the system thermal-hydraulics code RELAP5 and the nodal spatial kinetics code NESTLE. Preliminary validation of the code as an engineering simulator was performed using a series of NEA PWR control rod ejection and withdrawal problems. Real time performance for simulator applications was demonstrated for ...

Recent advances in the computational speed of engineering workstations have enabled the development of a real-time version of the RELAP5 [Beelman, 1996] nuclear plant simulation code with Laboratory Discretionary Research and Development (LDRD) funding. In addition, the INEL is also funding the development of an enhanced real-time version of the existing three-dimensional nodal neutron kinetics...

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The LSTF experiment simulating the SGTR accident at the Mihama Unit-2 reactor is analyzed using the RELAP5/MOD3.3 code. In the accident, and thus in the experiment, the ECC water was injected not only into the cold legs but into the upper plenum. Overall transients during the experiment such as pressures and fluid temperatures are simulated well by the code. The cold-leg fluid temperatures are ...

The nuclear community has coupled several three-dimensional Computational Fluid Dynamics (CFD) solvers with one-dimensional system thermal–hydraulic (STH) codes. This work proposes to replace the CFD solver by a reduced order model (ROM) reduce computational cost. code RELAP5-MOD3.3 and ROM of finite volume OpenFOAM are partitioned domain decomposition coupling algorithm using an implicit schem...

The modern direction in the study of safety nuclear power plants is to ensure maximum level detail process modeling with a satisfactory computational resources. One approaches such task solving coupled use special software required levels detail, for example, systemic thermohydraulic codes hydrodynamics codes.
 This article describes developed coupling module between system code RELAP5/Mod...

Magnetohydrodynamic (MHD) phenomena, due to the interaction between a magnetic field and moving electro-conductive fluid, are crucial for design of magnetic-confinement fusion reactors and, specifically, breeding blanket concepts that adopt liquid metals (LMs) as working fluids. Computational tools employed lead fusion-relevant physical analysis, but dedicated MHD code able simulate all phenome...

Today, most software applications, also in the nuclear field, come with a graphical user interface. Recently, the Symbolic Nuclear Analysis Package (SNAP) was designed to simplify the process of performing safety analysis. The purpose of the present study was to develop an SNAP animation model for RELAP5 calculations of a nuclear installation. The facility selected was the Rig of Safety Assessm...

A RELAP5-3D model has been developed for the RBMK Kursk 1 NPP. The primary features of this model are the three-dimensional neutronics model of the reactor core and the user subroutine that generates the neutron cross-sections. This subroutine contains the same neutron cross-section libraries that are presently being used in the Russian STEPAN/KOBRA calculations. The implementation of the neutr...