Zobrazeno 1 - 10
of 27
pro vyhledávání: '"Uwe Imke"'
Autor:
Manuel García, Radim Vočka, Riku Tuominen, Andre Gommlich, Jaakko Leppänen, Ville Valtavirta, Uwe Imke, Diego Ferraro, Paul Van Uffelen, Lukáš Milisdörfer, Victor Sanchez-Espinoza
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3133-3150 (2021)
This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results
Externí odkaz:
https://doaj.org/article/a33301b22f5342ef95b0f04cb031d091
Publikováno v:
Energies, Vol 15, Iss 4, p 1554 (2022)
In order to join efforts to develop high-fidelity multi-physics tools for research reactor analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed for power reactors. The coupled system uses the Monte Carlo Serpent
Externí odkaz:
https://doaj.org/article/98ebf32f9af64ad88e356f1607cc7707
Autor:
Uwe Imke, Victor Hugo Sanchez
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
SUBCHANFLOW is a computer code to analyze thermal-hydraulic phenomena in the core of pressurized water reactors, boiling water reactors, and innovative reactors operated with gas or liquid metal as coolant. As part of the ongoing assessment efforts,
Externí odkaz:
https://doaj.org/article/77f50c321b9f4fc8ac361b4e8085dc1c
Autor:
Jaakko Leppänen, Manuel García, Victor Sanchez-Espinoza, Riku Tuominen, Ville Valtavirta, Diego Ferraro, Uwe Imke
Publikováno v:
Ferraro, D, García, M, Imke, U, Valtavirta, V, Tuominen, R, Leppänen, J & Sanchez-Espinoza, V 2020, ' Serpent/subchanflow coupled burnup calculations for vver fuel assemblies ', EPJ Web of Conferences, vol. 247, pp. 713-720 . https://doi.org/10.1051/epjconf/202124704005
EPJ Web of Conferences, Vol 247, p 04005 (2021)
EPJ Web of Conferences, Vol 247, p 04005 (2021)
The continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ commercial goals represent a push for the development of highly accurate methodologies in reactor physics. This fact, combined with the availabi
Publikováno v:
Nuclear Engineering and Design. 390:111708
Publikováno v:
Nuclear Engineering and Design. 338:181-188
TWOPORFLOW is a thermal hydraulics code under development, which simulates two-phase flow in a structured or unstructured porous medium using a flexible 3-Dimensional Cartesian geometry. It has the capability to simulate simple 1-D geometries (like h
Autor:
Jaakko Leppänen, Lukáš Milisdörfer, Ville Valtavirta, Victor Sanchez-Espinoza, Diego Ferraro, Paul Van Uffelen, Andre Gommlich, Uwe Imke, Manuel García, Riku Tuominen, Radim Vočka
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3133-3150 (2021)
García, M, Vočka, R, Tuominen, R, Gommlich, A, Leppänen, J, Valtavirta, V, Imke, U, Ferraro, D, Van Uffelen, P, Milisdörfer, L & Sanchez-Espinoza, V 2021, ' Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor ', Nuclear Engineering and Technology, vol. 53, no. 10, pp. 3133-3150 . https://doi.org/10.1016/j.net.2021.04.023
Nuclear Engineering and Technology 53(2021), 3133-3150
Nuclear Engineering and Technology, 53 (10), 3133-3150
García, M, Vočka, R, Tuominen, R, Gommlich, A, Leppänen, J, Valtavirta, V, Imke, U, Ferraro, D, Van Uffelen, P, Milisdörfer, L & Sanchez-Espinoza, V 2021, ' Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor ', Nuclear Engineering and Technology, vol. 53, no. 10, pp. 3133-3150 . https://doi.org/10.1016/j.net.2021.04.023
Nuclear Engineering and Technology 53(2021), 3133-3150
Nuclear Engineering and Technology, 53 (10), 3133-3150
This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eeb001502e2e7cf7f1e661758d7632a8
Autor:
Diego Ferraro, Manuel García, Ville Valtavirta, Uwe Imke, Riku Tuominen, Jaakko Leppänen, Sanchez-Espinoza Victor
Publikováno v:
Ferraro, D, García, M, Valtavirta, V, Imke, U, Tuominen, R, Leppänen, J & Victor, S-E 2021, Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics . in Mathematics & Computation (M &C) 2021 ., 50027, American Nuclear Society (ANS), Transactions of the American Nuclear Society, no. 3141, pp. 549-558, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M &C 2021, Raleigh, North Carolina, United States, 11/04/21 . < https://www.ans.org/pubs/proceedings/article-50027/ >
VTT Technical Research Centre of Finland-PURE
VTT Technical Research Centre of Finland-PURE
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::25817cf95cd045dd01c653b58258f7ba
https://cris.vtt.fi/en/publications/b5cd1e03-a473-460f-b554-ed6cf212fafc
https://cris.vtt.fi/en/publications/b5cd1e03-a473-460f-b554-ed6cf212fafc
Autor:
Victor Sanchez-Espinoza, Y. Bilodid, Ville Valtavirta, Uwe Imke, Riku Tuominen, Manuel García, Diego Ferraro, Jaakko Leppänen
Publikováno v:
EPJ Web of Conferences, Vol 247, p 04006 (2021)
European Physical Journal Web of Conferences 247(2021), 04006
European Physical Journal Web of Conferences 247(2021), 04006
An increasing interest on the development of highly accurate methodologies in reactor physics is nowadays observed, mainly stimulated by the availability of vast computational resources. As a result, an on-going development of a wide range of coupled
Autor:
Riku Tuominen, Diego Ferraro, Uwe Imke, Victor Sanchez-Espinoza, Manuel García, Ville Valtavirta, Jaakko Leppänen
Publikováno v:
Ferraro, D, Valtavirta, V, García, M, Imke, U, Tuominen, R, Leppänen, J & Sanchez-Espinoza, V 2020, ' OECD/NRC PWR MOX/UO 2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW ', Annals of Nuclear Energy, vol. 147, 107745 . https://doi.org/10.1016/j.anucene.2020.107745
In this work, high-fidelity calculations using a recently developed coupled scheme between the Serpent 2 Monte Carlo transport code and the SUBCHANFLOW subchannnel thermal–hydraulic code are done for the well-known full core MOX/UO2 PWR OECD/NRC be