Petra Čejková - Academia.edu (original) (raw)
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Romanian Academy. Institute of Archaeology and History of Art of Cluj-Napoca
Centre National de la Recherche Scientifique / French National Centre for Scientific Research
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Papers by Petra Čejková
Metals
The presented work is aimed at the evaluation of the cold bending capacity of high-borated austen... more The presented work is aimed at the evaluation of the cold bending capacity of high-borated austenitic stainless steel sheets. Due to their excellent neutron-absorbing capability, borated stainless steels belong to the group of tailor-made structural materials widely used for vertical storage baskets for holding spent nuclear fuel assemblies in cooling pools at dry or wet storage facilities. The basket consists of individual fuel assembly cells. Each polygonal cell is usually welded from several steel strips. It would be advantageous to use bent steel semi-product to avoid welded seams as much as possible. Welded seams are difficult to make, and moreover, they are susceptible to corrosion. However, high-borated stainless steels, because of their boron content, show limited hot and cold workability. Thus, their cold bending capacity would be the primary issue. Their austenitic matrix with embedded hard and brittle boride particles is prone to the evolution and fast propagation of dimp...
Použité jaderné palivo ve formě palivových souborů nebo kazet je nutné po jeho vyjmutí z reaktoru... more Použité jaderné palivo ve formě palivových souborů nebo kazet je nutné po jeho vyjmutí z reaktoru nejprve uskladnit ve skladovacích bazénech po dobu několika let, následně jej umístit do transportně-skladovacího obalového souboru pro střednědobé skladování, a poté případně do obalového souboru pro trvalé uložení. K tomu jsou zapotřebí komponenty jako skladovací mříže, stínící prvky nebo koše obalových souborů, které jsou většinou vyrobeny z kovových materiálů s přídavkem bóru. Mikrostruktura korozivzdorných ocelí obohacených cca 2 hm. % bóru je charakteristická přítomností boridů Cr2B v austenitické matrici Fe-gama.Used nuclear fuel in the form of fuel assemblies or cartridges must be first stored in storage pools for several years after being removed from the reactor, then placed in a transport-storage package for medium-term storage, and then possibly in a permanent storage package. This requires components such as storage grids, shielding elements or baskets of packaging sets, wh...
The paper examines and compares the properties of laser clad deposits of Stellite 6 and Stellite ... more The paper examines and compares the properties of laser clad deposits of Stellite 6 and Stellite 21 on 1.4923 + QT base material which is often used for power generation components. Cladding was performed using two different bead widths on a 63 mm diameter shaft with and without pre-heating. The widths of the beads deposited by a laser welding head were 1 millimetre and 3 millimetres. Using EDX, chemical dilution between the clad beads and the base material was examined. The paper gives a detailed description of metallographic observation of the claddings and the heat-affected zone and correlates the findings with hardness values. It also presents results of wear analysis conducted at simulated service conditions at 550°C.
Metals
The presented work is aimed at the evaluation of the cold bending capacity of high-borated austen... more The presented work is aimed at the evaluation of the cold bending capacity of high-borated austenitic stainless steel sheets. Due to their excellent neutron-absorbing capability, borated stainless steels belong to the group of tailor-made structural materials widely used for vertical storage baskets for holding spent nuclear fuel assemblies in cooling pools at dry or wet storage facilities. The basket consists of individual fuel assembly cells. Each polygonal cell is usually welded from several steel strips. It would be advantageous to use bent steel semi-product to avoid welded seams as much as possible. Welded seams are difficult to make, and moreover, they are susceptible to corrosion. However, high-borated stainless steels, because of their boron content, show limited hot and cold workability. Thus, their cold bending capacity would be the primary issue. Their austenitic matrix with embedded hard and brittle boride particles is prone to the evolution and fast propagation of dimp...
Použité jaderné palivo ve formě palivových souborů nebo kazet je nutné po jeho vyjmutí z reaktoru... more Použité jaderné palivo ve formě palivových souborů nebo kazet je nutné po jeho vyjmutí z reaktoru nejprve uskladnit ve skladovacích bazénech po dobu několika let, následně jej umístit do transportně-skladovacího obalového souboru pro střednědobé skladování, a poté případně do obalového souboru pro trvalé uložení. K tomu jsou zapotřebí komponenty jako skladovací mříže, stínící prvky nebo koše obalových souborů, které jsou většinou vyrobeny z kovových materiálů s přídavkem bóru. Mikrostruktura korozivzdorných ocelí obohacených cca 2 hm. % bóru je charakteristická přítomností boridů Cr2B v austenitické matrici Fe-gama.Used nuclear fuel in the form of fuel assemblies or cartridges must be first stored in storage pools for several years after being removed from the reactor, then placed in a transport-storage package for medium-term storage, and then possibly in a permanent storage package. This requires components such as storage grids, shielding elements or baskets of packaging sets, wh...
The paper examines and compares the properties of laser clad deposits of Stellite 6 and Stellite ... more The paper examines and compares the properties of laser clad deposits of Stellite 6 and Stellite 21 on 1.4923 + QT base material which is often used for power generation components. Cladding was performed using two different bead widths on a 63 mm diameter shaft with and without pre-heating. The widths of the beads deposited by a laser welding head were 1 millimetre and 3 millimetres. Using EDX, chemical dilution between the clad beads and the base material was examined. The paper gives a detailed description of metallographic observation of the claddings and the heat-affected zone and correlates the findings with hardness values. It also presents results of wear analysis conducted at simulated service conditions at 550°C.