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,...
Date: 8-12 July 2024Place: Universitat de BarcelonaFacultat de FisicaDiagonal 64508028 Barcelona - SPAINMinimum enrolment: 6 participantsMaximum enrolment: 15 participantsCourse fee: 1500 EURRegistra...
This two-day online event will be...
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...
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...
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....
Photo credit: Joel A. Kulesza, Roger Lee Martz, LANL LA-UR-17-23854
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Dates: 12-13 April 2023
Location: Online course, 9:00-13:00 (CEST, UTC+02:00, Paris time)
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...
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...
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...
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 ...
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...