Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Rafał Bryk"'
Modeling of emergency condenser system response to loss of coolant accident in a BWR III+ generation
Publikováno v:
Eksploatacja i Niezawodność – Maintenance and Reliability. 21:468-475
Emergency Condenser (EC) is a heat exchanger composed of a large number of slightly inclined U-tubes arranged horizontally. The inlet header of the condenser is connected with the top part of the Reactor Pressure Vessel (RPV), which is occupied by st
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8ce2aba0e7e81293333bace6a556a26e
https://doi.org/10.17531/ein.2019.3.13
https://doi.org/10.17531/ein.2019.3.13
Publikováno v:
Eksploatacja i Niezawodność – Maintenance and Reliability. 21:28-36
Evaluation of the two-phase water mixture level in the case of the sudden depressurization of the Reactor Pressure Vessel resulting from an accident scenario is an important aspect in the reactor safety analysis. This paper discusses results of simul
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4f3cc4b8d3eae4a3def72a14e233291d
https://doi.org/10.17531/ein.2019.1.4
https://doi.org/10.17531/ein.2019.1.4
Publikováno v:
Archives of Thermodynamics, Vol 38, Iss 4, Pp 29-51 (2017)
KERENA is an innovative boiling water reactor concept equipped with several passive safety systems. For the experimental verification of performance of the systems and for codes validation, the Integral Test Stand Karlstein (INKA) was built in Karlst
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9530d68e79e678fc066cd1ebb0a62c35
http://www.degruyter.com/view/j/aoter.2017.38.issue-4/aoter-2017-0023/aoter-2017-0023.xml?format=INT
http://www.degruyter.com/view/j/aoter.2017.38.issue-4/aoter-2017-0023/aoter-2017-0023.xml?format=INT
Publikováno v:
Energy. 211:118612
PKL is a worldwide unique integral test facility for simulation of thermal-hydraulic phenomena, which can occur in Pressurized Water Reactor under abnormal or accident conditions. The test rig replicates the entire primary side and the relevant parts
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1100c65ad1bd66e79a2a6936680f429e
https://doi.org/10.1016/j.energy.2020.118612
https://doi.org/10.1016/j.energy.2020.118612
Publikováno v:
2018 International Interdisciplinary PhD Workshop (IIPhDW).
This paper discusses results obtained during the simulation of water dynamics and heat transfer during sudden depressurization of a vessel filled with water under the saturation conditions. Validated prediction of the thermal-hydraulics during the de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5096520a43d0eb172121910449d330c
https://doi.org/10.1109/iiphdw.2018.8388234
https://doi.org/10.1109/iiphdw.2018.8388234
Publikováno v:
E3S Web of Conferences, Vol 137, p 01016 (2019)
PKL is the only test facility in Europe that replicates the entire primary side and the most important parts of the secondary side of western-type Pressurized Water Reactors (PWR) in the scale of 1:1 in heights. It is also worldwide the only test fac
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6f10981d183e60cfe623de9bcb78ce5e
https://doi.org/10.1051/e3sconf/201913701016
https://doi.org/10.1051/e3sconf/201913701016
Publikováno v:
E3S Web of Conferences, Vol 137, p 01035 (2019)
INKA is a test facility designed by Framatome and built in the technical center in Karlstein. The original objective for establishing this test rig was the investigation of the performance of the passive safety systems developed in a new Framatome Bo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e79e53653f5f796d8e2d2b59d58082dc
https://doi.org/10.1051/e3sconf/201913701035
https://doi.org/10.1051/e3sconf/201913701035
Publikováno v:
ITM Web of Conferences, Vol 15, p 03007 (2017)
The condensation in horizontal tubes plays an important role in determining the operation mode of passive safety systems of modern nuclear power plants. In this paper, two different approaches for modelling of this phenomenon are compared and verifie
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5acc19c2904eee740540cdaf86b441f4
https://doi.org/10.1051/itmconf/20171503007
https://doi.org/10.1051/itmconf/20171503007