Zobrazeno 1 - 10
of 442
pro vyhledávání: '"Ferroukhi H"'
Publikováno v:
EPJ Web of Conferences, Vol 247, p 02034 (2021)
Currently, safety analyses mostly rely on codes which solve both the neutronics and the thermal-hydraulics with assembly-wise nodes resolution as multiphysics heterogeneous transport solvers are still too time and memory expensive. The pin-by-pin hom
Externí odkaz:
https://doaj.org/article/02f0cc4c47c446989c9478e85348e0d9
Publikováno v:
EPJ Web of Conferences, Vol 247, p 10004 (2021)
Assessing neutron emission of LWR spent fuel is necessary for the back-end of the fuel cycle, such as the dimensioning of transport and storage casks of spent fuel. Although core and depletion codes can calculate the isotopic composition of the disch
Externí odkaz:
https://doaj.org/article/4873716afa294238a74163173bfddce5
Publikováno v:
EPJ Web of Conferences, Vol 247, p 06011 (2021)
The main goal of this work is to perform pin-by-pin calculations of Swiss LWR fuel assemblies with neutron transport deterministic methods. At Paul Scherrer Institut (PSI), LWR calculations are performed with the core management system CMSYS, which i
Externí odkaz:
https://doaj.org/article/669ebc1e30314301afcd5df91ca8d3d5
Publikováno v:
EPJ Web of Conferences, Vol 247, p 10021 (2021)
The CASMO/SIMULATE/MCNP/FISPACT-II calculation route has been established at the Paul Scherrer Institute (PSI) for reactor dosimetry and activation studies. Furthermore, the in-house tool NUSS is in use at PSI for nuclear data (ND) related uncertaint
Externí odkaz:
https://doaj.org/article/c8421024f8b646149d5990aff46e7f09
Publikováno v:
EPJ Web of Conferences, Vol 247, p 21008 (2021)
Some of the KWU pre-KONVOI PWRs operating across Europe saw a systematic increase in the neutron noise levels over several cycles in the last decade, and subsequently, core internals’ movements, especially vibrations of fuel assemblies with specifi
Externí odkaz:
https://doaj.org/article/472d52019c1b4f5fbfe76f15131387bc
Autor:
Alhassan E., Rochman D., Vasiliev A., Bergmann R.M., Wohlmuther M., Koning A.J., Ferroukhi H.
Publikováno v:
EPJ Web of Conferences, Vol 239, p 13005 (2020)
A lot of research work has been carried out in fine tuning model parameters to reproduce experimental data for neutron induced reactions. This however is not the case for proton induced reactions where large deviations still exist between model calcu
Externí odkaz:
https://doaj.org/article/d19c1ed85adb4f75bae3dc6409e9b420
Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
Publikováno v:
EPJ Web of Conferences, Vol 146, p 09028 (2017)
In the design of a spent nuclear fuel disposal system, one necessary condition is to show that the configuration remains subcritical at time of emplacement but also during long periods covering up to 1,000,000 years. In the context of criticality saf
Externí odkaz:
https://doaj.org/article/290249ec59974f2a93b512f1d6b1beb4
Autor:
Rochman D., Koning A.J., Sublet J.Ch., Fleming M., Bauge E., Hilaire S., Romain P., Morillon B., Duarte H., Goriely S., van der Marck S.C., Sjöstrand H., Pomp S., Dzysiuk N., Cabellos O., Ferroukhi H., Vasiliev A.
Publikováno v:
EPJ Web of Conferences, Vol 146, p 02006 (2017)
The TALYS Evaluated Nuclear Data Library (TENDL) has now 8 releases since 2008. Considerable experience has been acquired for the production of such general-purpose nuclear data library based on the feedback from users, evaluators and processing expe
Externí odkaz:
https://doaj.org/article/d3ca3c172c7e4aaba67e0b38d7e2512c
Publikováno v:
In Annals of Nuclear Energy 1 December 2024 208
Publikováno v:
In Progress in Nuclear Energy July 2024 172