Thermalhydraulic and neutronic calculations are the basis for deterministic safety analyses (DSA) performed by Department of Nuclear Safety at TES. We employ a number of tools and codes commonly used in many engineering and power producing companies, research institutes and regulatory authorities worldwide:
- RELAP5 – one-dimensional system code for the analysis of transients and accidents in NPP
- TRACE – multidimensional system code for the analysis of transients and accidents in NPP
- MELCOR – engineering-level computer code for the analysis of the progression of severe accidents in NPP
- PARCS – neutronics code for 3D analyses of reactor core
- SCALE/TRITON – code for steady-state and time-dependent lattice physics analyses
- ALTHAM C – thermalhydraulic subchannel code
- COBRA TF – thermalhydraulic subchannel code
- ANSYS Fluent – universal multidisciplinary CFD code
- OpenFOAM – universal multidisciplinary CFD codeOther supportive SW:
- SNAP – GUI for model development and pre/post processing
- AptPlot – WYSIWYG 2D plotting tool
- ACAP – statistical code for benchmarking of NPP models
CAMP a CSARP
The workhorses of our calculational analyses are the computer codes shared in frame of U.S. NRC’s international cooperation programmes CAMP (Code Applications and Maintenance Program) and CSARP (Cooperative Severe Accident Research Program). Within these programmes TES participates on further development and independent validation of aforementioned codes.
State Office for Nuclear Safety certification (SÚJB)
Any entity performing safety calculations for nuclear installation must undergo the certification of the computer code and its users by the Czech nuclear regulatory authority (SUJB). TES has successfully obtained such certification to use the codes RELAP5/MOD3.3, TRACE V5.0 a MELCOR 2.1, which makes us one of a few companies allowed to perform the safety assessment of Czech NPPs.
TES experts have developed number of input decks for analyses of nuclear power plants, including comprehensive models of complete NPP units. Following list highlights the most important models:
All models have been validated against data from real operation or commissioning tests or test from experimental facilities of ITF/SETF type.