Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Seyed Mohsen Hoseyni"'
Publikováno v:
Kerntechnik. 87:398-408
Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different acci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b4e052ffc767a1afc2153bcfd911a0b1
https://doi.org/10.1515/kern-2022-0007
https://doi.org/10.1515/kern-2022-0007
Publikováno v:
Physics of Fluids. 34:123326
Fluid infiltration, solidification, and remelting in a particle bed are complex phenomena that can occur in the lower head of a reactor pressure vessel (an in-vessel phenomenon) or in the reactor cavity below the vessel (an ex-vessel phenomenon) duri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6170b48925f0371b01c09ad317a38c6a
https://doi.org/10.1063/5.0124983
https://doi.org/10.1063/5.0124983
Autor:
Akinobu Morita, Michael Buck, Andrei Komlev, Akitoshi Hotta, Per Sköld, Seyed Mohsen Hoseyni, Toshinori Matsumoto, Miyuki Akiba, Tomoyuki Sugiyama, Sachin Thakre, Alexander Konovalenko, Walter Villanueva, Sevostian Bechta
Publikováno v:
Journal of Nuclear Science and Technology. 57:353-369
Key phenomena in the cooling states of underwater debris beds were classified based on the premise that a target debris bed has a complicated geometry, nonhomogeneous porosity, and volumetric heat....
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::db29a0ba9fa943ea5ebebc63c9e60ecc
https://doi.org/10.1080/00223131.2019.1691078
https://doi.org/10.1080/00223131.2019.1691078
Autor:
Andrei Komlev, Seyed Mohsen Hoseyni, Sachin Thakre, Sevostian Bechta, Akitoshi Hotta, Alexander Konovalenko, Miyuki Akiba, Walter Villanueva, Per Sköld
Publikováno v:
Nuclear Engineering and Design. 379:111229
The re-melting of multi-component debris is important for both in-vessel and ex-vessel phases of severe accident progression in nuclear power plants. However, current knowledge is limited with respect to understanding the associated complex phenomena
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f1e225c38f0aa5ad3b1c22f9ead7d894
https://doi.org/10.1016/j.nucengdes.2021.111229
https://doi.org/10.1016/j.nucengdes.2021.111229
Publikováno v:
Kerntechnik. 82:289-302
Development of a steady-state model is the first step in nuclear safety analysis. The developed model should be qualitatively analyzed first, then a sensitivity analysis is required on the number of nodes for models of different systems to ensure the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68b79e96e47ddbdea1cb04d3d939d2f0
https://doi.org/10.3139/124.110627
https://doi.org/10.3139/124.110627
Publikováno v:
Kerntechnik. 82:67-77
This paper deals with simulation, sensitivity and uncertainty analysis of LP-FP-2 experiment of LOFT test facility. The test facility simulates the major components and system response of a pressurized water reactor during a LOCA. MELCOR code is used
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9c28ab47bf58f1e9650041ccfb475413
https://doi.org/10.3139/124.110610
https://doi.org/10.3139/124.110610
Publikováno v:
International Journal of Hydrogen Energy. 42:7104-7119
This paper deals with determination of the minimum number and identification of the best configurations of passive autocatalytic recombiners (PAR) for the effective design of the containment in a pressurized water reactor (PWR). It considers the curr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ebf11ac2c8212a5f7d5de25f3bb4b47b
https://doi.org/10.1016/j.ijhydene.2017.01.110
https://doi.org/10.1016/j.ijhydene.2017.01.110
Publikováno v:
International Journal of System Assurance Engineering and Management. 8:635-645
Success criteria analysis in nuclear power plants is based on thermo-hydraulics (TH) evaluation of the plant response to postulated accidents for the development of a risk model. PRA (Probabilistic Risk Assessment) uncertainties originate from divers
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e8563ce2d46b7661781ad6b29751803f
https://doi.org/10.1007/s13198-016-0547-7
https://doi.org/10.1007/s13198-016-0547-7
Publikováno v:
International Journal of System Assurance Engineering and Management. 8:625-634
To study the capacity of reactor containment under pressurization, it is important to know the way that this structure reacts under internal pressure loading. This is usually performed through structural fragility analysis for assuring that the conta
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97dd147a749c23ce5499c8f3dbe7e3c6
https://doi.org/10.1007/s13198-016-0540-1
https://doi.org/10.1007/s13198-016-0540-1
Publikováno v:
Nuclear Engineering and Design. 305:400-410
In application to thermal–hydraulic calculations by system codes, sensitivity analysis plays an important role for managing the uncertainties of code output and risk analysis. Sensitivity analysis is also used to confirm the results of qualitative
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8d4c7020c53b9d0f25079fcb6bd6ad99
https://doi.org/10.1016/j.nucengdes.2016.05.032
https://doi.org/10.1016/j.nucengdes.2016.05.032