| Lasso Monte Carlo, a variation on multi fidelity methods for high-dimensional uncertainty quantification
Albà, A., Boiger, R., Rochman, D., & Adelmann, A. (2025). Lasso Monte Carlo, a variation on multi fidelity methods for high-dimensional uncertainty quantification. Journal of Applied Statistics, 1-37. https://doi.org/10.1080/02664763.2025.2487505 |
| Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo
Albà, A., Adelmann, A., & Rochman, D. (2025). Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo. Annals of Nuclear Energy, 211, 110892 (17 pp.). https://doi.org/10.1016/j.anucene.2024.110892 |
| Towards a new generation of solid total-energy detectors for neutron-capture time-of-flight experiments with intense neutron beams
Balibrea-Correa, J., Babiano-Suarez, V., Lerendegui-Marco, J., Domingo-Pardo, C., Ladarescu, I., Tarifeño-Saldivia, A., … Žugec, P. (2025). Towards a new generation of solid total-energy detectors for neutron-capture time-of-flight experiments with intense neutron beams. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1072, 170110 (14 pp.). https://doi.org/10.1016/j.nima.2024.170110 |
| Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions
Berry, L., Vasiliev, A., Rochman, D., Hursin, M., Frankl, M., & Ferroukhi, H. (2025). Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions. Annals of Nuclear Energy, 211, 110939 (14 pp.). https://doi.org/10.1016/j.anucene.2024.110939 |
| Application of backward differential formula and Anderson's method for multigroup diffusion transient equation
Cherezov, A., Vasiliev, A., & Ferroukhi, H. (2025). Application of backward differential formula and Anderson's method for multigroup diffusion transient equation. Annals of Nuclear Energy, 210, 110837 (19 pp.). https://doi.org/10.1016/j.anucene.2024.110837 |
| Towards high-fidelity high-resolution modeling of a BWR fuel assembly by CASMO-5
Cherezov, A., Vasiliev, A., & Ferroukhi, H. (2025). Towards high-fidelity high-resolution modeling of a BWR fuel assembly by CASMO-5. Annals of Nuclear Energy, 213, 111072 (16 pp.). https://doi.org/10.1016/j.anucene.2024.111072 |
| <em>k<sub>eff</sub></em> behaviour of a potential PWR assembly loaded disposal canister in simplified corrosion scenarios
Frankl, M., Berry, L., Vasiliev, A., Rochman, D., Ferroukhi, H., Diomidis, N., & Wittel, M. (2025). keff behaviour of a potential PWR assembly loaded disposal canister in simplified corrosion scenarios. Nuclear Engineering and Design, 437, 114007 (12 pp.). https://doi.org/10.1016/j.nucengdes.2025.114007 |
| Finding limiting rods for dry storage analyses
Konarski, P., Cherezov, A., Cozzo, C., Khvostov, G., & Ferroukhi, H. (2025). Finding limiting rods for dry storage analyses. Annals of Nuclear Energy, 212, 111043 (18 pp.). https://doi.org/10.1016/j.anucene.2024.111043 |
| Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark
Kwon, S. J., Papadionysiou, M., Jung, Y. S., Rouxelin, P., Vasiliev, A., Ferroukhi, H., … Shim, H. J. (2025). Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark. Annals of Nuclear Energy, 220, 111532 (15 pp.). https://doi.org/10.1016/j.anucene.2025.111532 |
| New insights on fission of <sup>235</sup>U induced by high energy neutrons from a new measurement at n_TOF
Manna, A., Pirovano, E., Console Camprini, P., Cosentino, L., Dietz, M., Ducasse, Q., … Žugec, P. (2025). New insights on fission of 235U induced by high energy neutrons from a new measurement at n_TOF. Physics Letters B, 860, 139213 (8 pp.). https://doi.org/10.1016/j.physletb.2024.139213 |
| Verification of nTRACER/COBRA-TF with Serpent2/SUBCHANFLOW for full core high fidelity high-resolution analysis of VVERs
Papadionysiou, M., Bilodid, Y., Fridman, E., Pautz, A., & Hursin, M. (2025). Verification of nTRACER/COBRA-TF with Serpent2/SUBCHANFLOW for full core high fidelity high-resolution analysis of VVERs. Nuclear Engineering and Design, 433, 113855 (15 pp.). https://doi.org/10.1016/j.nucengdes.2025.113855 |
| Adjusting JEFF-3.3 actinide data using a new, dedicated methodology for selecting suited assimilation database parameters
Pelloni, S., & Rochman, D. (2025). Adjusting JEFF-3.3 actinide data using a new, dedicated methodology for selecting suited assimilation database parameters. Annals of Nuclear Energy, 215, 111246 (11 pp.). https://doi.org/10.1016/j.anucene.2025.111246 |
| Adjusting aluminum elastic scattering data from the TALYS nuclear reaction code based upon fast criticalities
Pelloni, S., & Rochman, D. (2025). Adjusting aluminum elastic scattering data from the TALYS nuclear reaction code based upon fast criticalities. Annals of Nuclear Energy, 211, 111000 (11 pp.). https://doi.org/10.1016/j.anucene.2024.111000 |
| Building bridges between nuclear reactions and statistical models
Rochman, D. (2025). Building bridges between nuclear reactions and statistical models. In P. Dimitriou, R. Capote, & G. Schnabel (Eds.), EPJ web of conferences: Vol. 322. International workshop on compound-nuclear reactions and related topics (p. 01003 (3 pp.). https://doi.org/10.1051/epjconf/202532201003 |
| TENDL-astro: a new nuclear data set for astrophysics interest
Rochman, D., Koning, A., Goriely, S., & Hilaire, S. (2025). TENDL-astro: a new nuclear data set for astrophysics interest. Nuclear Physics A, 1053, 122951 (11 pp.). https://doi.org/10.1016/j.nuclphysa.2024.122951 |
| What to expect from microscopic nuclear modelling for k<sub>eff</sub> calculations?
Rochman, D., Koning, A., Goriely, S., & Hilaire, S. (2025). What to expect from microscopic nuclear modelling for keff calculations? Nuclear Physics A, 1054, 122979 (9 pp.). https://doi.org/10.1016/j.nuclphysa.2024.122979 |
| Measurement of the prompt neutron decay constant in a zero-power reactor using a novel 3D detector system
Saliba, M., Lamirand, V., Monange, W., Vitullo, F., Hursin, M., Pautz, A., & Pakari, O. (2025). Measurement of the prompt neutron decay constant in a zero-power reactor using a novel 3D detector system. Nuclear Science and Engineering. https://doi.org/10.1080/00295639.2025.2456411 |
| Applicability domain and gaps of SNF decay heat validation data – a similarity-based approach
Shama, A., Caruso, S., & Rochman, D. A. (2025). Applicability domain and gaps of SNF decay heat validation data – a similarity-based approach. Annals of Nuclear Energy, 211, 110905 (16 pp.). https://doi.org/10.1016/j.anucene.2024.110905 |
| Fast uncertainty quantification of spent nuclear fuel with neural networks
Albà, A., Adelmann, A., Münster, L., Rochman, D., & Boiger, R. (2024). Fast uncertainty quantification of spent nuclear fuel with neural networks. Annals of Nuclear Energy, 196, 110204 (8 pp.). https://doi.org/10.1016/j.anucene.2023.110204 |
| Uncertainty quantification on spent nuclear fuel with LMC
Albà, A., Adelmann, A., & Rochman, D. (2024). Uncertainty quantification on spent nuclear fuel with LMC. In K. Suyama, S. Gunji, T. Watanabe, S. Araki, K. Fukuda, K. Shimada, … H. H. Nguyen (Eds.), Proceedings of the 12th international conference on nuclear criticality safety (pp. 1-10). Japan Atomic Energy Agency. |
