Výsledky vyhledávání - "Stanisz Przemysław"

Akademický článek

Fission chambers for space effect reduction in the application of the area method: A new approach

Autor: Janczyszyn Jerzy A., Domańska Grażyna, Stanisz Przemysław

Publikováno v: Nukleonika, Vol 65, Iss 3, Pp 161-166 (2020)

The possibility of preparing fission chambers for the experimental determination of subcriticality without time-consuming corrections has been presented. The reactor detectors set consists of monoisotopic chambers. Each chamber is intended for a spec

Externí odkaz: https://doaj.org/article/86811c143cdd48e4b9128498efb60217

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Akademický článek

Radionuclide neutron source trajectories in the closed nuclear fuel cycle

Autor: Stanisz Przemysław, Cetnar Jerzy, Oettingen Mikołaj

Publikováno v: Nukleonika, Vol 64, Iss 1, Pp 3-9 (2019)

The highest efficiency in the usage of nuclear energy resources can be implemented in fast breeder reactors of generation IV. It is achieved thanks to the ability of consuming minor actinides (MAs) in energy production. One of the options to use this

Externí odkaz: https://doaj.org/article/8102f903442b4b7397cc540158607415

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Akademický článek

Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source

Autor: Oettingen Mikołaj, Stanisz Przemysław

Publikováno v: Nukleonika, Vol 63, Iss 3, Pp 87-91 (2018)

This paper describes the methodology developed for the numerical reconstruction and modelling of the thorium-lead (Th-Pb) assembly available at the Department of Nuclear Energy, Faculty of Energy and Fuels, AGH University, Krakow, Poland. This numeri

Externí odkaz: https://doaj.org/article/5179c72c913d48b48e1a67fcda9e9641

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Akademický článek

Modeling minor actinide multiple recycling in a lead-cooled fast reactor to demonstrate a fuel cycle without long-lived nuclear waste

Autor: Stanisz Przemysław, Cetnar Jerzy, Domańska Grażyna

Publikováno v: Nukleonika, Vol 60, Iss 3, Pp 581-590 (2015)

The concept of closed nuclear fuel cycle seems to be the most promising options for the efficient usage of the nuclear energy resources. However, it can be implemented only in fast breeder reactors of the IVth generation, which are characterized by t

Externí odkaz: https://doaj.org/article/10303880a7614a7183088ad26e1cc432

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Akademický článek

Validation of VHTRC calculation benchmark of critical experiment using the MCB code

Autor: Stanisz Przemysław, Malicki Mateusz, Kopeć Mariusz

Publikováno v: E3S Web of Conferences, Vol 10, p 00123 (2016)

The calculation benchmark problem Very High Temperature Reactor Critical (VHTR) a pin-in-block type core critical assembly has been investigated with the Monte Carlo Burnup (MCB) code in order to validate the latest version of Nuclear Data Library ba

Externí odkaz: https://doaj.org/article/40ba6f1fe68b45149fcfdb36c717cfc8

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