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Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
Alhassan, E., Rochman, D., Sjöstrand, H., Vasiliev, A., Koning, A. J., & Ferroukhi, H. (2020). Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo. Annals of Nuclear Energy, 139, 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
Andreani, M., Kapulla, R., Kelm, S., Paladino, D., & Paranjape, S. (2020). Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code. Journal of Nuclear Engineering and Radiation Science, 6(2), 021110 (18 pp.). https://doi.org/10.1115/1.4046296
The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs
Hombourger, B., Křepel, J., & Pautz, A. (2020). The EQL0D fuel cycle procedure and its application to the transition to equilibrium of selected molten salt reactor designs. Annals of Nuclear Energy, 144, 107504 (18 pp.). https://doi.org/10.1016/j.anucene.2020.107504
Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques
Hursin, M., Pakari, O., Perret, G., Frajtag, P., Lamirand, V., Pázsit, I., … Pautz, A. (2020). Measurement of the gas velocity in a water-air mixture in CROCUS using neutron noise techniques. Nuclear Technology. https://doi.org/10.1080/00295450.2019.1701906
Treatment of the implicit effect in Shark-X
Hursin, M., Pelloni, S., Vasiliev, A., & Ferroukhi, H. (2020). Treatment of the implicit effect in Shark-X. Annals of Nuclear Energy, 138, 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Kalilainen, J., Nichenko, S., & Krepel, J. (2020). Evaporation of materials from the molten salt reactor fuel under elevated temperatures. Journal of Nuclear Materials, 533, 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Khvostov, G. (2020). Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2020.05.015
Analytical criteria for fuel fragmentation and burst FGR during a LOCA
Khvostov, G. (2020). Analytical criteria for fuel fragmentation and burst FGR during a LOCA. Nuclear Engineering and Technology. https://doi.org/10.1016/j.net.2020.03.009
Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
Khvostov, G. (2020). Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code. Nuclear Engineering and Technology, 52(1), 135-147. https://doi.org/10.1016/j.net.2019.07.010
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Kim, W., Hursin, M., Pautz, A., Vincent, L., Pavel, F., & Lee, D. (2020). Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor. Annals of Nuclear Energy, 136, 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
A summary of fission-product-transport phenomena during SGTR severe accidents
Lind, T., Campbell, S., Herranz, L. E., Kissane, M., & Song, J. H. (2020). A summary of fission-product-transport phenomena during SGTR severe accidents. Nuclear Engineering and Design, 363, 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
Measurement of the <sup>154</sup>Gd(n,<em>γ</em>) cross section and its astrophysical implications
Mazzone, A., Cristallo, S., Aberle, O., Alaerts, G., Alcayne, V., Amaducci, S., … Žugec, P. (2020). Measurement of the 154Gd(n,γ) cross section and its astrophysical implications. Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics, 804, 135405 (6 pp.). https://doi.org/10.1016/j.physletb.2020.135405
Calculation of <em>λ</em> modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
Morató, S., Bernal, Á., Miró, R., Roman, J. E., & Verdú, G. (2020). Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method. Annals of Nuclear Energy, 137, 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
Assessment of nTRACER and PARCS performance for VVER configurations
Papadionysiou, M., Seongchan, K., Hursin, M., Vasiliev, A., Ferroukhi, H., Pautz, A., & Joo, H. G. (2020). Assessment of nTRACER and PARCS performance for VVER configurations. Nuclear Science and Engineering. https://doi.org/10.1080/00295639.2020.1753418
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
Pellegrini, M., Herranz, L., Sonnenkalb, M., Lind, T., Maruyama, Y., Gauntt, R., … Mizokami, S. (2020). Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project. Nuclear Technology. https://doi.org/10.1080/00295450.2020.1724731
Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
Pelloni, S., & Rochman, D. (2020). Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method. Annals of Nuclear Energy, 145, 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
Rochman, D., Koning, A. J., & Sublet, J. C. (2020). A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019. Nuclear Data Sheets, 163, 163-190. https://doi.org/10.1016/j.nds.2019.12.003
Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
Rochman, D., Dokhane, A., Vasiliev, A., Ferroukhi, H., & Hursin, M. (2020). Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics. European Physical Journal Plus, 135, 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
The OFFBEAT multi-dimensional fuel behavior solver
Scolaro, A., Clifford, I., Fiorina, C., & Pautz, A. (2020). The OFFBEAT multi-dimensional fuel behavior solver. Nuclear Engineering and Design, 358, 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Siefman, D., Hursin, M., Perret, G., & Pautz, A. (2020). Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments. Progress in Nuclear Energy, 121, 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
 

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