Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...
Dates: 12-13 April 2023
Location: Online course, 9:00-13:00 (CEST, UTC+02:00, Paris time)
Dates: 3-7 April, 2023Place: OECD Headquarters in Paris, FranceMinimum enrollment required: 12 participants Course fee: 1000 EURThis 4.5-day interactive course is intended to give students a thorough...
This advanced course is designed for people who have experience in running MCNP Monte Carlo calculations, but who would like to advance their skills and develop greater depth of understanding of theo...
***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...
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
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 ...
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 was addressed to researchers in Radiation Physics and its applications. The main objective was to provide the participants with a detailed description of PENELOPE, with an ample perspecti...
