- Status
- Closed
Summary
This project consisted of the transfer of calculation codes for VVER-1000 from German experts to the Ukrainian Nuclear Regulatory Body (at that time GANU). The project included code handling qualification (using of German codes by Ukrainian experts), definition of training plans, accuracy assessment, upgrading of calculation codes and code modification according to the specific requirements of GANU. Finally the codes were implemented in an adequate computer in STCS (Technical Support Organization).
The concerned codes were:
NESSEL 4: Spectrum and micro burn-up calculation code for preparation of neutronphysical characteristics for stationary and instationary core conditions
FLEX: 2D fine mesh diffusion code for neutron flux and power distribution calculation of VVER Fuel element assemblies
DYN3D-M2: Code for calculation of the dynamic VVER reactor core behaviour for short-time processes like reactivity-initiated accidents
PYKIA: 3D Macro burn-up calculation code used for VVER cores in the scope of loading, reloading, fuel management, core design and safety related measures
NUKO: Code for the calculation of fuel nuclide inventory (heavy nuclides and fission products) of VVER, RBMK and CANDU fuel pins
DERAB: Code for the calculation of neutron flux, power density and burn-up distribution within VVER fuel elements
TRAPEZ: 3D macro burn-up calculation code on advanced nodal method used in the scope of core design
STEZ: code for calculation of boundary conditions for plane, cylindrical and hexagonal assemblies on the basis of an analytical method
PREPAR: code for preparation of input data for fine and coarse mesh codes basing on NESSEl-4 results.
The project included also the supply of a workstation.