Davidenko V.D., Ioannisian M.V.
National Research Center "Kurchatov institute", Moscow, Russia
The description of the test tasks developed for verification of space-time kinetic codes focused on water-water reactors is presented in the article. The geometry of calculated area represents the lattice of fuel pins, infinite in the radial. The model is close to critical and has the sizes of the VVER-1000 reactor with a boundary condition "vacuum" at end faces. Transient is induced into the system due to the instantaneous input or output of the absorber (10B) in the water on a half of height of the fissile region. The inputs of a positive, negative and "zero" reactivities are considered.
The presented tasks are transparent both on geometry of calculated area, and on the description of the material structure and transient processes, "are convenient" for use of both a diffusion, and transport approximation and allow to carry out calculations, both taking into account heterogeneity and homogenization.
The results of calculations with programs, using a Monte-Carlo method, both for direct Monte-Carlo operation (KIR code), and by method of a multipoint kinetics (MRNK code) are provided. They can be used as the fiducial for verification of the programs using various approximate solution methods of the neutron transfer equation.
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