Zobrazeno 1 - 10
of 53
pro vyhledávání: '"DAVOR GRGIĆ"'
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:
Journal of Energy : Energija
Volume 62
Issue 1-4
Volume 62
Issue 1-4
The system code ATHLET (Analysis of THermal-hydraulics of Leaks and Transients) is being developed by the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) mbH in Garching, Germany. In the paper, an overview of activities performed at Faculty of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e3b004425c931b207259521d22078a32
https://doi.org/10.37798/2013621-4218
https://doi.org/10.37798/2013621-4218
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 1-2
Volume 65
Issue 1-2
This paper presents comparison of the Krško Power Plant simplified Spent Fuel Pool (SFP) dose rates using different computational shielding methodologies. The analysis was performed to estimate limiting gamma dose rates on wall mounted level instrum
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::80c2cd72e80ff939ca84c4bd247b1580
https://doi.org/10.37798/2016651-2138
https://doi.org/10.37798/2016651-2138
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
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 8
In this paper, shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW (Holtec International Transfer Cask Variable Weight) loaded with spent fuel assemblies (SFA) from nuclear power plant (NPP)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::875e406087173a2dcc2c66d4442145a5
https://doi.org/10.1115/1.4051447
https://doi.org/10.1115/1.4051447