Zobrazeno 1 - 10
of 318
pro vyhledávání: '"fuel assemblies"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 4, Pp 24-00188-24-00188 (2024)
The Japan Atomic Energy Agency (JAEA) is developing an evaluation method for a two-phase flow in the reactor core using simulation codes based on the volume of fluid (VOF) method. However, it is impossible to simulate boiling on the heating surface i
Externí odkaz:
https://doaj.org/article/27fb75e9d4a94bbf91d0c8fe37a18527
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 6, Pp 2088-2095 (2023)
The safety of nuclear installations is largely determined by the tightness of fuel elements cladding. As the Fukushima nuclear accident showed, the main task in case of loss of power supply is to ensure reliable removal of residual heat release from
Externí odkaz:
https://doaj.org/article/b9968051f75e4cb797ef3483562b8ab9
Autor:
Leturcq, Bertrand, Le Tallec, Patrick
Publikováno v:
Comptes Rendus. Mécanique, Vol , Iss , Pp 1-17 (2023)
The numerical simulation of multiscale and multiphysics problems requires efficient tools for spatial localization and model reduction. A general strategy combining Domain Decomposition and Nonuniform Transformation Field Analysis (NTFA) is proposed
Externí odkaz:
https://doaj.org/article/a2bd62cf542b4c3fb96e2e5ea49f1815
Autor:
Sibongiseni Thabethe
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 36, Pp 231-236 (2022)
The effective management of spent fuel pool (SFP) safety has been raised as one of the emerging issues to further enhance nuclear installation safety after the Fukushima accident on March 11, 2011. SFP safety-related issues have been mainly focused o
Externí odkaz:
https://doaj.org/article/6b7eb9ee53094858a2f43d4b532d6708
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Publikováno v:
Journal of Nuclear Engineering, Vol 2, Iss 2, Pp 207-214 (2021)
In this paper, the conceptual design and a preliminary study of the LUT Heating Experimental Reactor (LUTHER) for 2 MWth power are presented. Additionally, commercially sized designs for 24 MWth and 120 MWth powers are briefly discussed. LUTHER is a
Externí odkaz:
https://doaj.org/article/41b019e883db4d7da5c7c76d43fab4d3
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 888-893 (2021)
The International Atomic Energy Agency has developed a tomographic imaging system for accomplishing the total fuel rod-by-rod verification time of fuel assemblies within the order of 1–2 h, however, there are still limitations for some fuel types.
Externí odkaz:
https://doaj.org/article/06f6c9c601ec444dba827bca83a5b3d0
Publikováno v:
مجله علوم و فنون هستهای, Vol 41, Iss 4, Pp 138-145 (2020)
The multi-objective optimization methods are widely used in various areas of science and engineering. In this paper, a multi-objective optimization algorithm has been used to design the optimal placement of fuel assemblies in the KWU reactor with the
Externí odkaz:
https://doaj.org/article/98bc96baade146979916d46069f85255
Autor:
S. M. Dmitriev, A. V. Gerasimov, A. A. Dobrov, D. V. Doronkov, A. N. Pronin, A. V. Ryazanov, D. N. Solntsev, A. E. Khrobostov
Publikováno v:
Izvestiâ Vysših Učebnyh Zavedenij i Ènergetičeskih ob Edinennij SNG. Ènergetika, Vol 63, Iss 2, Pp 151-162 (2020)
The article presents the results of experimental studies of the local hydrodynamics of the coolant flow in the mixed core of the VVER reactor, consisting of the TVSA-T and TVSA-T mod.2 fuel assemblies. Modeling of the flow of the coolant flow in the
Externí odkaz:
https://doaj.org/article/ee143919c6c24ae7828537009eab734f
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.