IRDF-2002 crossection library issued by IAEA in 2006, which supersedes older IRDF-90/V2 version is analyzed. Library contains crossections and other data used for analysis of neutron flux.
COBISS.SI-ID: 208686447
New method of precise determination of concrete biological shield activation is described. Method is based on precise neutron field calculation.
COBISS.SI-ID: 18700071
A study of density packing of fuel pebbles in a "pebble bed" reactor was performed. WIMS and MCNP codes were used. Study gives directions for a fourth generation of power reactors design.
COBISS.SI-ID: 20061991
Physiscal and computational of a critical experiment performed by Batelle Pacific was performed. Monte Carlo simulation results (code MCNP) show excellent agreement with the experiment
COBISS.SI-ID: 19818791
Monte Carlo method for dose dsitribution calculation for radiotherapy was developed. Method is already in clinical use in USA.
COBISS.SI-ID: 19686695
IRDF-2002 crossection library issued by IAEA in 2006, which supersedes older IRDF-90/V2 version is analyzed. Library contains crossections and other data used for analysis of neutron flux.