Zobrazeno 1 - 10
of 139
pro vyhledávání: '"K. VELKOV"'
Autor:
W. ZWERMANN, A. AURES, L. GALLNER, V. HANNSTEIN, B. KRZYKACZ-HAUSMANN, K. VELKOV, J.S. MARTINEZ
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 3, Pp 343-352 (2014)
Uncertainty and sensitivity analyses with respect to nuclear data are performed with depletion calculations for BWR and PWR fuel assemblies specified in the framework of the UAM-LWR Benchmark Phase II. For this, the GRS sampling based tool XSUSA is e
Externí odkaz:
https://doaj.org/article/9480665478ce4a6b8fcffa6660316376
Publikováno v:
Journal of Applied Ichthyology. 38:114-117
SKETCH-N/ATHLET steady-state and dynamic coupling scheme verification on Kalinin-3 benchmark results
Autor:
V. I. Romanenko, Vyacheslav G. Zimin, Romain Henry, Sergey Nikonov, Georgy Tikhomirov, K. Velkov, Yann Perin
Publikováno v:
Kerntechnik. 85:265-273
The paper describes the multi-physics coupling scheme between the SKETCH-N nodal neutronics code and the best-estimate thermohydraulic code ATHLET v3.2. Some first results are discussed. Various possible options of coupling have been considered. A sc
Publikováno v:
Kerntechnik. 84:316-321
The OECD/NEA Benchmark on NPP Kalinin Unit 3 “Switching-off of one of the four operating main circulation pumps at nominal power” based on measurements is at its end phase. A new benchmark is starting based on measurements from the NPP Rostov Uni
Publikováno v:
Transactions of the American Nuclear Society - Volume 123.
Autor:
Yann Perin, K. Velkov
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 6, Pp 1339-1345 (2017)
In the framework of the EU funded project NURESAFE, the subchannel code CTF and the neutronics code DYN3D were integrated and coupled on the NURESIM platform. The developments achieved during this 3-year project include assembly-level and pin-by-pin
Publikováno v:
Kerntechnik. 81:427-431
An uncertainty and sensitivity analysis is performed for the OECD/NEA coolant transient Benchmark (K-3) on measured data at Kalinin-3 Nuclear Power Plant (NPP). A switch off of one main coolant pump (MCP) at nominal reactor power is calculated using
Publikováno v:
Kerntechnik. 81:105-116
Over 60 technical experts of the reactor safety research division of the Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH are developing and validating reliable methods and computer codes – summarized under the term nuclear simulation c
Autor:
Sergei Pavlovich Nikonov, K. Velkov, V. I. Romanenko, R. Henry, Vyacheslav G. Zimin, Y. Perin
Publikováno v:
Journal of Physics: Conference Series. 1689:012058
The paper describes recent developments in the multi-physics coupling scheme between the SKETCH-N nodal neutronics code and the best-estimate thermohydraulic code ATHLET v3.2. The boundary conditions plugin was implemented. The verification and valid
Publikováno v:
Nuclear Engineering and Design. 362:110584
Best Estimate Plus Uncertainty (BEPU), as an approach, involves predictive simulations in a safety assessment processes. Since the very beginning (80s) when the best estimate simulations have been firstly accepted in a safety assessment it has been a