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pro vyhledávání: '"I. Panka"'
Akademický článek
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Autor:
P. Mikoláš, J. Vimpel, V. Krýsl, A. I. Shcherenko, J. Švarný, D. Sprinzl, R. Vočka, I. Pós, I. Panka, Jiří Závorka, K. Y. Kurakin
Publikováno v:
Kerntechnik. 83:282-293
This work deals with “Full-Core” VVER-440 extended calculation benchmark which was proposed on the 24th Symposium of AER in October 2014 [2]. This benchmark is based on calculation benchmark defined by ŠKODA JS a.s. on the 21st Symposium of AER
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42e37d8d212679ec39f5615e7f40930f
https://doi.org/10.3139/124.110901
https://doi.org/10.3139/124.110901
Publikováno v:
Kerntechnik. 83:365-375
In VVER-1000/1200 type reactors much higher and geometrically more complex assemblies are applied compared to the VVER-440 design. Additionally, assembly shrouds are not used in the improved reactor types. This implies that the existing sub-channel w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00f6f7a7e42084077122c91825d11391
https://doi.org/10.3139/124.110899
https://doi.org/10.3139/124.110899
Publikováno v:
Kerntechnik. 82:517-526
The best-estimate KARATE code system has been widely used for core design calculations and simulations of slow transients of VVER reactors. Recently there has been an increasing need for assessing the uncertainties of such calculations by propagating
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::18e5497b2b4844a76ef57df5e6829b01
https://doi.org/10.3139/124.110826
https://doi.org/10.3139/124.110826
Publikováno v:
Kerntechnik. 82:461-467
For calculation of the radiological consequences of Large Break Loss of Coolant (LBLOCA) events, a set of various computer codes modeling the corresponding physical processes, disciplines and their appropriate subsequent data exchange are necessary.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d211ecb66bd660f76fd42fe01232b948
https://doi.org/10.3139/124.110819
https://doi.org/10.3139/124.110819
Publikováno v:
Kerntechnik. 81:418-426
The best estimate simulation of three-dimensional phenomena in nuclear reactor cores requires the use of coupled neutron physics and thermal-hydraulics calculations. However these analyses should be supplemented by the survey of the corresponding unc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1372051a1ab4956c40c97e0c75b86844
https://doi.org/10.3139/124.110711
https://doi.org/10.3139/124.110711
Autor:
I. Panka, A. Keresztúri
Publikováno v:
Kerntechnik. 80:305-313
Defining precisely the burnup of the nuclear fuel is important from the point of view of core design calculations, safety analyses, criticality calculations (e. g. burnup credit calculations), etc. This paper deals with the uncertainties of MULTICELL
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1cd0c6adf15626b939e74dc768c60fe
https://doi.org/10.3139/124.110501
https://doi.org/10.3139/124.110501
Publikováno v:
Kerntechnik. 79:351-358
The fulfillment of the safety analysis acceptance criteria and the normal operation safety related limitations are usually evaluated by using separate hot-channel or/and hot-assembly thermal hydraulic calculations, especially for the closed VVER-440
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b289920e2928a2707dc63638ed4df3db
https://doi.org/10.3139/124.110459
https://doi.org/10.3139/124.110459
Autor:
A. Keresztúri, I. Panka
Publikováno v:
Kerntechnik. 79:359-366
The assessment of the uncertainties of COBRA-IIIC thermal-hydraulic analyses of rod bundles is performed for a 5-by-5 bundle representing a PWR fuel assembly. In the first part of the paper the modeling uncertainties are evaluated in the term of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6b7410ddbac60bb6941b79a90e50c07a
https://doi.org/10.3139/124.110460
https://doi.org/10.3139/124.110460
Autor:
I. Panka, A. Keresztúri
Publikováno v:
Kerntechnik. 78:300-309
In this paper the uncertainties of the neutronic calculations at core level – originating from the uncertainties of the basic nuclear data – are presented. The investigations have been made for a VVER-1000 core (Kozloduy-6) defined in the frame o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::51a1e34ab227f2b025b9f985f68f4a7e
https://doi.org/10.3139/124.110378
https://doi.org/10.3139/124.110378