Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Katarzyna Skolik"'
Publikováno v:
Annals of Nuclear Energy. 128:44-52
The AP1000 is currently an advanced pressurized water reactor with emergency core cooling systems (ECCS) completely dependent on natural circulation. It is under construction in the USA and has been commissioned in China and is being considered by se
Autor:
Judith Hohorst, Marina Perez-Ferragut, Chris M. Allison, Ludwik Pieńkowski, Katarzyna Skolik, Mateusz Malicki, A.K. Trivedi
Publikováno v:
Progress in Nuclear Energy. 134:103648
Small Modular Reactors (SMRs) are currently being developed and licensed in many countries. The innovations in the designs provide many significant features, such as decreased construction cost and time, enhanced safety, modularity, possibility of fa
Publikováno v:
Volume 6B: Thermal-Hydraulics and Safety Analyses.
The NuScale Small Modular Reactor (SMR) is an integrated Pressurized Water Reactor (iPWR) with the coolant flow based on the natural circulation. The reactor core consists of 37 fuel assemblies similar to those used in typical PWRs, but only half of
Publikováno v:
IOP Conference Series: Earth and Environmental Science. 214:012071
Safety of Nuclear Power Plants (NPPs) is one of the main issues in nuclear industry mainly because of the probability of radionuclides release to the environment. Due to this fact nuclear safety is continuously being improved by vendors to face the g
Publikováno v:
E3S Web of Conferences, Vol 108, p 01023 (2019)
Future development of the energy conversion systems will be based on second and third generation technology. Additionally, modern power plants are expected to be able to work in a very wide range of power output. At the same time, frequent and rapid
Autor:
Katarzyna Skolik, Mikołaj Oettingen
Publikováno v:
E3S Web of Conferences, Vol 10, p 00118 (2016)
In the paper we present the study on the dependence of actinides concentrations in the spent nuclear fuel on FIMA burnup. The concentrations of uranium, plutonium, americium and curium isotopes obtained in numerical simulation are compared with the r
Publikováno v:
E3S Web of Conferences, Vol 10, p 00105 (2016)
High temperature gas-cooled nuclear reactor (called HTR or HTGR) for both electricity generation and hydrogen production is analysed. The HTR reactor because of the relatively high temperature of coolant could be combined with a steam or gas turbine,
Autor:
Mikołaj Oettingen, Katarzyna Skolik
Publikováno v:
E3S Web of Conferences, Vol 10, p 00067 (2016)
In the paper we present the Monte Carlo modelling by the means of the Monte Carlo Continuous Energy Burn-up Code of the 17x17 Pressurized Water Reactor fuel assembly designed according to the Radkowsky Thorium Fuel concept. The design incorporates th