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...
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...
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,...
PHITS (Particle and Heavy Ion Transport code System) is a general purpose Monte Carlo particle transport simulation code developed under a collaboration between Japan Atomic Energy Agency (JAEA) and ...
This training course provides instruction on the use of the KENO-VI Monte Carlo code for criticality safety calculations and the MAVRIC (Monaco with Automated Variance Reduction using Importance Calc...
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 ...
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
***The course is full***
This intermediate course is designed for people who have some experience in running MCNP Monte Carlo calculations, but who would like to refresh or advance their skills. Prov...