Uncertainty Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA
Author:
Affiliation:
1. SCK CEN, Belgian Nuclear Research Centre, Mol, Belgium
2. Université Libre de Bruxelles, Service de Métrologie Nucléaire, Brussels, Belgium
Publisher
Informa UK Limited
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295639.2024.2353987
Reference41 articles.
1. L. FIORITO et al., “Novel Neutronics Design of the MYRRHA Core,” presented at the Int. Conf. on Fast Reactors and Related Fuel Cycles FR22: Sustainable Clean Energy for the Future (CN-291), Vienna, Austria (2022).
2. L. FIORITO et al., “Temperature Reactivity Feedback Coefficients for the MYRRHA Critical Core - Design Revision 1.8,” presented at ICNC 2023—The 12th Int. Conf. on Nuclear Criticality Safety, Sendai, Japan (2023).
3. Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients
4. Sensitivity and uncertainty analyses for advanced nuclear systems (ALFRED, ASTRID, ESFR and MYRRHA)
5. Nuclear data uncertainty propagation on a sodium fast reactor
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