Zobrazeno 1 - 10
of 21
pro vyhledávání: '"SINIŠA ŠADEK"'
Publikováno v:
Energies, Vol 15, Iss 5, p 1842 (2022)
A comprehensive uncertainty analysis in the event of a severe accident in a two-loop pressurized water reactor is conducted using an uncertainty package integrated in the ASYST code. The plant model is based on the nuclear power plant (NPP) Krško, a
Externí odkaz:
https://doaj.org/article/8e961d4e4d7f481da17e60a270ea9d1f
Publikováno v:
Energies, Vol 13, Iss 2, p 359 (2020)
Electromagnetic compatibility (EMC) in nuclear power plants today mostly relies on the qualification tests of the new equipment and adhering to some good installation practices. Diversity of the electromagnetic environment and different susceptibilit
Externí odkaz:
https://doaj.org/article/0c9f8f20ce3a495b8413814790a16251
Publikováno v:
Energies, Vol 12, Iss 11, p 2176 (2019)
Containment is the last barrier for release of radioactive materials in the case of an accident in the nuclear power plant (NPP). Its overall integrity is tested during a containment integrated leak rate test (CILRT) at the design pressure, at regula
Externí odkaz:
https://doaj.org/article/58ba3d3d9f024476b0458b6c3967e017
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
The integrity of the containment will be challenged during a severe accident due to pressurization caused by the accumulation of steam and other gases and possible ignition of hydrogen and carbon monoxide. Installation of a passive filtered venting s
Externí odkaz:
https://doaj.org/article/efa8bcb8d66a44fdada77f9f89a79a2a
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2010 (2010)
RELAP5/SCDAPSIM and MAAP4 are two widely used severe accident computer codes for the integral analysis of the core and the reactor pressure vessel behaviour following the core degradation. The objective of the paper is the comparison of code results
Externí odkaz:
https://doaj.org/article/2504b7317fef48d0bc7784e454b1d52d
Publikováno v:
Journal of Energy - Energija. 68:209-219
For a large Spent Fuel Pool (SFP) loss of coolant accidents, properly sized SFP spray can slowdown or possibly preclude fast heat-up of spent fuel. The MELCOR 2.1 model of NPP Krsko pool was developed and tested for cases of loss of cooling accidents
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4036230af13531902c095c9bab9a8ab7
https://doi.org/10.37798/2019682-3204
https://doi.org/10.37798/2019682-3204
Publikováno v:
Journal of Energy - Energija. 64:90-101
The automatic procedure was developed for fuel assembly decay heat calculation based on PARCS 3D burnup calculation for fuel cycle depletion, and ORIGEN 2.1 calculation during both depletion and fuel cooling. Using appropriate pre-processor and post-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89a2d6785f6f87df98c3158032fc0670
https://doi.org/10.37798/2015641-4146
https://doi.org/10.37798/2015641-4146
Publikováno v:
Journal of Energy : Energija
Volume 65
Issue 3-4
Volume 65
Issue 3-4
The analysis of a Station blackout (SBO) accident in the NPP Krško including thermalhydraulic behaviour of the primary system and the containment, as well as the simulation of the core degradation process, release of molten materials and production
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eda777b18202003c329620c4a3e919ec
https://doi.org/10.37798/2016653-4117
https://doi.org/10.37798/2016653-4117
Autor:
A. Marušić, Perica Ilak, Ghislain Trullenque, Siniša Šadek, Ivan Rajšl, Sara Raos, Tena Bilić
Publikováno v:
Mediterranean Conference on Power Generation, Transmission, Distribution and Energy Conversion (MEDPOWER 2018)
This paper presents the main characteristics of a decision-making support tool for economic and environmental assessment of enhanced geothermal systems given a particular site. The tool examines the enhanced geothermal systems projects in a holistic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::12242fa8fd85623ce3e042d1bd15da33
https://zenodo.org/record/5793896
https://zenodo.org/record/5793896
The baffle jetting phenomenon, intensified by pressure difference across baffle plates, may cause excessive fuel rod vibrations and possible damage. The downward flow direction through the baffle-barrel region opposite to the upward flow through the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8f6a69f9de644c6178441d695ea2fbd4
https://www.bib.irb.hr/1081727
https://www.bib.irb.hr/1081727