Issue |
EPJ Web of Conf.
Volume 294, 2024
WONDER-2023 - 6th International Workshop On Nuclear Data Evaluation for Reactor applications
|
|
---|---|---|
Article Number | 05005 | |
Number of page(s) | 7 | |
Section | Uncertainties and Covariance Matrices | |
DOI | https://doi.org/10.1051/epjconf/202429405005 | |
Published online | 17 April 2024 |
https://doi.org/10.1051/epjconf/202429405005
Application of nuclear data covariance matrices to representativity calculations
1 SCK CEN, Belgian nuclear research center, Boeretang 200, 2400 Mol, Belgium
2 Université libre de Bruxelles, Avenue F.D. Roosevelt, 50, 1050 Bruxelles
3 CEA Saclay, DES/Scientific Division Energies F-91191 Gif-Sur-Yvette
* e-mail: federico.grimaldi@sckcen.be
Published online: 17 April 2024
The neutronics design of new reactors has been historically relying on zero power research reactors for the simulation of the core irradiation conditions as well as for nuclear data and code validation. In this framework, a study on the possible MYRRHA representativity improvement coming from the loading of MOX fuel in VENUS-F zero power reactor is under investigation. This work analyses the effect of the nuclear data used in the sensitivity and representativity calculations, highlighting the need for a comprehensive set of nuclides and reactions to be further studied.
© The Authors, published by EDP Sciences, 2024
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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