Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Ivanov KO"'
Publikováno v:
EPJ Web of Conferences, Vol 302, p 12004 (2024)
This paper shows models developed and results obtained for neutronics simulations of the 3D core of C5G7-TD Benchmark using the Serpent code, and an approach for multi-physics coupling for Serpent/CTF codes was presented. Neutronic simulations includ
Externí odkaz:
https://doaj.org/article/8c69013e84c245fa97ef3a2e375759fe
Autor:
Takasugi Cole, Martin Nicolas, Labouré Vincent, Ortensi Javier, Ivanov Kostadin, Avramova Maria
Publikováno v:
EPJ Nuclear Sciences & Technologies, Vol 9, p 15 (2023)
The generation of accurate kinetic parameters such as mean generation time Λ and effective delayed neutron fraction βeff via Monte Carlo codes is established. Employing these in downstream deterministic codes warrants another step to ensure no addi
Externí odkaz:
https://doaj.org/article/480e1985ad1445b99a4014a1b80ae2b0
Autor:
Ivanov Konstantin
Publikováno v:
Magazine of Civil Engineering, Vol 108, Iss 08 (2021)
Thermal insulation materials are widely used in engineering practice to reduce the depth of seasonal freezing. The effective thermal conductivity of the material is the main criterion for predicting the freezing depth of the structure base and determ
Externí odkaz:
https://doaj.org/article/460d069487d344daac823a0cd911f5be
Autor:
Valentine Timothy, Avramova Maria, Fleming Michael, Hursin Mathieu, Ivanov Kostadin, Petruzzi Alessandro, Rohatgi Upendra, Velkov Kiril
Publikováno v:
EPJ Web of Conferences, Vol 247, p 06048 (2021)
The OECD Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC) established the Expert Group on Multi-physics Experimental Data, Benchmarks and Validation (EGMPEBV) in 2014 to bridge the gap between advanced, multi-physics simulation capabilitie
Externí odkaz:
https://doaj.org/article/e1e97254322f42d8a85f7483d2fd243e
Publikováno v:
EPJ Web of Conferences, Vol 247, p 10034 (2021)
The utilization of liquid metals as coolants for fast reactors brings several economical and practical advantages that lead to a sustainable future for nuclear energy. Molten sodium is used as a coolant in Sodium Fast Reactors (SFRs). Sodium is relat
Externí odkaz:
https://doaj.org/article/3bb0219623774ccf943913f131417071
Publikováno v:
EPJ Web of Conferences, Vol 247, p 03008 (2021)
Accurate reactor core steady state safety analysis requires coupling between thermal-hydraulics and three dimensional multigroup pin by pin neutronics. Concerning the neutronics modeling, the Nodal Expansion Method (NEM) code is developed at North Ca
Externí odkaz:
https://doaj.org/article/780a41cbaa84495e9ae683ba28b71d67
Publikováno v:
Meditsinskaia tekhnika [Med Tekh] 2015 Jan-Feb (1), pp. 30-2.