Nuclear Systems Physics

Organisational unit: Expert Group

  1. 2020
  2. The nuclear fuel cycle code ANICCA: Verification and a case study for the phase out of Belgian nuclear power with minor actinide transmutation

    Merino Rodríguez, I., Hernandez Solis, A., Messaoudi, N. & Van den Eynde, G., 13 Apr 2020, (Accepted/In press) In : Nuclear Engineering and Design. p. 1-11 11 p.

    Research output: Contribution to journalArticle

  3. A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca

    Hernandez Solis, A., Merino Rodriguez, I., Fiorito, L. & Van den Eynde, G., 29 Mar 2020, PHYSOR 2020: Transition to a Scalable Nuclear Future. Unknown, p. 1-8 8 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  4. Boundary condition modeling effect on the spent fuel characterization and final decay heat prediction from a PWR assembly

    Hernandez Solis, A., Fiorito, L., Stankovskiy, A., Ambrozic, K., Calic, D., Kos, B., Kromar, M., Schillebeeckx, P., Stankovskiy, A. & Zerovnik, G., 29 Mar 2020, Unknown. Unknown, p. 1-10 10 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  5. Verification of the OpenMC homogenized MYRRHA-1.6 core model

    Hernandez Solis, A., Malambu Mbala, E., Stankovskiy, A. & Van den Eynde, G., 29 Mar 2020, PHYSOR 2020: Transition to a Scalable nuclear future. Unknown, p. 1-1 11 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  6. Reduced order modelling using a POD-based identification method for parametrized PDEs

    Van den Eynde, G., Belloni, F., Star, S., Degroote, J. & Vierendeels, J., 1 Mar 2020, Proceedings of the 6th European Conference on Computational Mechanics: Solids, Structures and Coupled Problems, ECCM 2018 and 7th European Conference on Computational Fluid Dynamics, ECFD 2018. CIMNE - International Centre for Numerical Methods in Engineering, p. 796-805 10 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  7. 2019
  8. Nuclear data analyses for improving the safety of advanced lead-cooled reactors

    Romojaro, P. & Krása, A., 6 Nov 2019, Universidad Politécnica de Madrid. 184 p.

    Research output: ThesisDoctoral thesis

  9. Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies

    Villacorta Skarbeli, A., Merino Rodriguez, I., Alvarez Velarde, F., Hernandez Solis, A. & Van den Eynde, G., 30 Oct 2019, In : Annals of nuclear energy. 137, p. 1-9 9 p., 107160.

    Research output: Contribution to journalArticle

  10. IRDFF-II: A New Neutron Metrology Library

    Malambu Mbala, E., Wagemans, J., Trkov, A., Griffin, P. J., Simakov, S. P., Greenwood, L. R., Zolotarev, K. I. & Capote Noy, R., 7 Sep 2019, In : Nuclear Data Sheets. p. 1-109 109 p.

    Research output: Contribution to journalArticle

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