Zobrazeno 1 - 10
of 12
pro vyhledávání: '"György Ézsöl"'
Publikováno v:
Measurement. 171:108787
The paper contains experimental data and analysis of the velocity distribution and pressure drop of turbulent flow through a fuel bundle of 19 rods as a partial model of the VVER-440 reactor core. Also, results from the code calculations at the outle
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8e458c797de7d0dfc491777184c467c3
https://doi.org/10.1016/j.measurement.2020.108787
https://doi.org/10.1016/j.measurement.2020.108787
Publikováno v:
Thermal Science, Vol 21, Iss 3, Pp 1491-1502 (2017)
Thermal fatigue and pressurized thermal shock phenomena are the main problems for the reactor pressure vessel and the T-junctions both of them depend on the mixing of the coolant. The mixing process, flow and temperature distribution has been investi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::24d23c96643c3257fdc3997cd5d23499
http://www.doiserbia.nb.rs/img/doi/0354-9836/2017/0354-98361500121H.pdf
http://www.doiserbia.nb.rs/img/doi/0354-9836/2017/0354-98361500121H.pdf
Publikováno v:
Nuclear Technology. 191:136-150
Pressure waves might be expected in a nuclear reactor system due to a sudden rupture of a pipe or to quick opening or closure of a system valve. Once generated, they can result in large mechanical loads on the reactor pressure vessel internal structu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8e698a95160dd10092ad10190d9c8f17
https://doi.org/10.13182/nt14-55
https://doi.org/10.13182/nt14-55
Publikováno v:
Thermal Science, Vol 19, Iss 3, Pp 989-1004 (2015)
The aim of this work is to investigate experimentally the increase of mixing phenomenon in a coolant flow in order to improve the heat transfer, the economical operation and the structural integrity of Light Water Reactors-Pressurized Water Reactors
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ad12e8ef9e629d99a9afd529ad02120c
http://www.doiserbia.nb.rs/img/doi/0354-9836/2015/0354-98361400051H.pdf
http://www.doiserbia.nb.rs/img/doi/0354-9836/2015/0354-98361400051H.pdf
Publikováno v:
Advanced Materials Research. :1054-1058
A coolant mixing investigation in a head of a half-size model of VVER-440 fuel assembly (simulator) has been performed at KFKI. The PIV and PLIF measurements have been done under a selected list of power distribution options, flow rates and powers. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be3daa0d7456c934fa2edfc4828b0278
https://doi.org/10.4028/www.scientific.net/amr.816-817.1054
https://doi.org/10.4028/www.scientific.net/amr.816-817.1054
Publikováno v:
Nuclear Engineering and Design. 240:1569-1574
During a loss of coolant accident (LOCA) the pressure of the coolant can drop significantly in the vicinity of the leak. It will be shown that unlike in pressurized water reactors (PWRs) where this pressure drop can cause only sudden vaporization - a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dd5e8ff8b07f003fcbf2b76d6114a985
https://doi.org/10.1016/j.nucengdes.2010.03.008
https://doi.org/10.1016/j.nucengdes.2010.03.008
Publikováno v:
Nuclear Engineering and Design. 240:266-274
Selected condensation-induced water hammer experiments performed on PMK-2 device were numerically modelled with three-dimensional two-fluid models of computer codes NEPTUNE_CFD and CFX. Experimental setup consists of the horizontal pipe filled with t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28ff916031df73d32ab58a2f3272d32e
https://doi.org/10.1016/j.nucengdes.2008.12.004
https://doi.org/10.1016/j.nucengdes.2008.12.004
Publikováno v:
Nuclear Engineering and Design. 240:146-150
We investigate the steam condensation induced water hammer (CIWH) phenomena and present experimental and theoretical results. The experiments were performed in the PMK-2 facility, which is a full-pressure thermo-hydraulic model of the primary loop of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b762749afc29330aae472131fbf2752
https://doi.org/10.1016/j.nucengdes.2009.09.027
https://doi.org/10.1016/j.nucengdes.2009.09.027
Publikováno v:
Volume 2B: Thermal Hydraulics.
Propagation of pressure waves inside the reactor vessel after a large break LOCA is an issue since it affects pressure drop across core internals and, as a result, induces stresses in different components, like core barrel, core structures and even f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::59b4892c2408dc61623a8276758e34e5
https://doi.org/10.1115/icone22-30706
https://doi.org/10.1115/icone22-30706
Publikováno v:
Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security.
The pressure waves might be expected in the nuclear reactor systems due to sudden rupture of a pipe, quick opening or closure of a system valve. If generated, they can result in large mechanical loads on the RPV internal structures and pipelines, thr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::13bc96b10ef6f03ee0a10a196d819112
https://doi.org/10.1115/icone22-30658
https://doi.org/10.1115/icone22-30658