Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Vojtech Rypar"'
Autor:
Michal Košťál, Evžen Losa, Stanislav Simakov, Martin Schulc, Jan Šimon, Vojtech Rypar, Martin Mareček, Jan Uhlíř, Tomáš Czakoj, Andrej Trkov, Roberto Capote
Publikováno v:
Annals of Nuclear Energy
The cross section averaged over 235U thermal-neutron induced fission spectrum is a fundamental quantity that can be used in evaluation and validation of nuclear data. Many experiments focused on the determination of Spectrum Averaged Cross Sections (
Autor:
Vlastimil Juricek, Zdenek Matej, Ladislav Viererbl, Evzen Losa, Vojtech Rypar, Michal Kostal, Filip Mravec, Jaroslav Šoltés, František Cvachovec, Martin Schulc
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 5
With increasing needs of neutron detection in energy and homeland security sectors, there is an aim in the development of new suitable detection materials with possible n/g separation and also satisfactory resolution. This issue is connected with a w
Autor:
Michal Košt'ál, Ján Milcák, Vojtech Rypar, Vlastimil Jurícek, Evzen Novák, Antonín Kolros, František Cvachovec, Sergey Zaritski
Publikováno v:
Progress in Nuclear Science and Technology. 4:317-321
Michal Kosťal, Jan Milcak, Vojtěch Rypar, Vlastimil Juřicek, Evžen Novak, Antonin Kolros, Frantisek Cvachovec and Sergey Zaritski Research Center Rez Ltd., 250 68 Husinec-Rez 130, Czech Republic; CTU in Prague, Faculty of Nuclear Sciences and Phy
Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor
Autor:
Michal Kostal, Tomas Bily, Evzen Losa, Martin Schulc, Nicola Burianová, Vojtech Rypar, Jan Šimon
Publikováno v:
Applied Radiation and Isotopes. 154:108855
The spectral averaged cross section is an important quantity used in a validation of nuclear cross section. When the cross sections are averaged over the neutron standard field (252Cf(s,f) or 235U(n,f) neutron spectrum), they can be used for tuning o
Autor:
Andrej Trkov, Michal Kostal, Roberto Capote, Jan Uhlíř, Tomas Bily, Martin Schulc, Evzen Losa, Martin Mareček, Stanislav Simakov, Tomáš Czakoj, Vojtech Rypar, Jan Šimon
Publikováno v:
Annals of Nuclear Energy
Cross section data are fundamental quantities which affect the accuracy of all calculations in nuclear applications. A new dosimetry library IRDFF-II that contains cross section evaluations with full uncertainty quantification was developed by the In