Open Access
| 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 | |
- A. Kochetkov et al., Integral experiments in the VENUS-F reactor, Annals of Nuclear Energy 157 (2021) [Google Scholar]
- L. Fiorito et al., Novel neutronics design of the MYRRHA core, International Conference on Fast Reactors and Related Fuel Cycles (2022) [Google Scholar]
- P. Blaise et al., An application of sensitivity and representativity approach for the design of a 100%MOX BWR experimental program in ZPR, Annals of Nuclear Energy 163 (2021) [Google Scholar]
- J. Leppänen et al, The Serpent Monte Carlo code: Status, development and applications in 2013, Annals of Nuclear Energy 82 (2015) [Google Scholar]
- D. Foligno, JEFF-4 evolution: from JEFF-3.3 to JEFF-4T2, OECD/NEA jefdoc-2210 (2022) [Google Scholar]
- K. Shibata et al., JENDL-4.0: A New Library for Nuclear Science and Engineering, Journal of Nuclear Science and Technology 48 (2011) [Google Scholar]
- D. A. Brown et al., ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) [Google Scholar]
- F. Grimaldi et al., MOX assembly design at the VENUS-F reactor for the representativity study of MYRRHA, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (publication accepted in 2023) [Google Scholar]
- A. Trkov et al., ENDF-6 Formats Manual, National Nuclear Data Center Brookhaven National Laboratory [Google Scholar]
- P. Romojaro et al., Report on sensitivity analysis of MYRRHA with list of key reactions, Seventh framework programme of the European atomic energy community [Google Scholar]
- M. Preston et al., MYRRHA, Fuel depletion, Simulation, Nuclear safeguards, Fast reactor, Non-destructive assay (NDA), Annals of Nuclear Energy 163 (2021) [Google Scholar]
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.