Now showing items 1-3 of 3
Verification of safety rod calculations by experiments on the RB reactor
(Society for Electronics,Telecommunications, Automation, and Nuclear Engineering, 1987)
Safety rod calculations performed by computation codes for global reactor core analysis were verified on experimental results obtained by measurements on RB reactor Three-dimensional code TRITON and two-dimensional codes ...
The application of the finite element method to the multigroup two-dimensional neutron diffusion equation on the KONEL code
(Society for Electronics,Telecommunications, Automation, and Nuclear Engineering, 1986)
The application of finite element method in space dependent neutron diffusion equation is shown in this paper The diffusion equation is first discretized using rectangular elements Applying piecewise polynomials in a ...
VAMPIR - dvogrupni dvodimenzioni program za proračun izgaranja nuklearng goriva u jezgru reaktora
(Society for Electronics,Telecommunications, Automation, and Nuclear Engineering, 1985)
VAMPIR is a computer code which simulates the burnup within a reactor coe It computes the neutron flux, power distribution and burnup taking into account spatial variations of temperature and xenon poisoning Its overall ...