OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code. It is capable of performing fixed source, k-eigenvalue and subcritical multiplication calculations on models ...
This course is addressed to researchers in Radiation Physics and its applications. The main objective is to provide the participants with a detailed description of the new, 2020, version of PENELOPE,...
FISPACT-II (currently at release version 5.0) is an enhanced multi-physics platform providing a wide variety of advanced simulation methods and employing the most up to date (TENDL-2019, ENDF/B-VIII....
OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code. It is capable of performing fixed source, k-eigenvalue, and subcritical multiplication calculations on models...
Overview of FRENDY
FRENDY (FRom Evaluated Nuclear Data librarY to any application) is a system to process evaluated nuclear data library and generate cross section library for transport codes. Featur...
NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...
This course is addressed to researchers in Radiation Physics and its applications. The main objective is to provide the participants with a detailed description of PENELOPE, with an ample perspective...
