P2-0073 — Final report
1.
Kodeli, I.A, Trkov, A.: Validation of the IRDF-2002 Dosimetry Library

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
2.
Žagar, T., Božič, M., Ravnik, M.: Long-lived Activation Products in TRIGA Mark II Research Reactor Concrete Shield

New method of precise determination of concrete biological shield activation is described. Method is based on precise neutron field calculation.

COBISS.SI-ID: 18700071
3.
Snoj, L., Ravnik, M.: Effect of Packing Fraction Variations on the Multipication Factor in Pebble-Bed Nuclear Reactors

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
4.
Lengar, I., Tomazin, M., Ravnik, M. Jeraj, R.: Water Reflected Triangular Pitched Lattice of Mixed Oxyde Fuel Rods Immersed in ...

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
5.
Jeraj, R., Mackie, T. R., Balog, J., Olivera, G. H.: Dose Calibration of Nonconventional Tratments Applied to Helical Tomotherapy

Monte Carlo method for dose dsitribution calculation for radiotherapy was developed. Method is already in clinical use in USA.

COBISS.SI-ID: 19686695
6.
Kodeli, I.A, Trkov, A.: Validation of the IRDF-2002 Dosimetry Library

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.