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Bohumil Jánský
Publications - 24
Citations - 155
Bohumil Jánský is an academic researcher. The author has contributed to research in topics: Neutron & Nuclear data. The author has an hindex of 7, co-authored 22 publications receiving 140 citations.
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Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor
Michal Košťál,Martin Veškrna,František Cvachovec,Bohumil Jánský,Evžen Novák,Vojtěch Rypar,Ján Milčák,Evžen Losa,Filip Mravec,Zdeněk Matěj,Jiří Rejchrt,Benoit Forget,Sterling Harper +12 more
TL;DR: In this paper, the authors compared the calculated and measured spectra after insertion of candidate materials for the Molten salt reactor/Fluoride cooled high temperature reactor system concept into the LR-0 reactor.
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On similarity of various reactor spectra and 235U prompt fission neutron spectrum.
Michal Košťál,Zdeněk Matěj,Evžen Losa,Ondřej Huml,Milan Štefánik,František Cvachovec,Martin Schulc,Bohumil Jánský,Evžen Novák,Davit Harutyunyan,Vojtěch Rypar +10 more
TL;DR: A new evaluation of thermal-neutron induced 235U PFNS was performed by the International Atomic Energy Agency (IAEA) in the CIELO (Collaborative International Evaluated Library Organisation Project) project; new measurements of Spectral Averaged Cross sections averaged in the evaluated spectrum are to be obtained.
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Neutron deep penetration through reactor pressure vessel and biological concrete shield of VVER-1000 Mock-Up in LR-0 reactor
Michal Košťál,František Cvachovec,Bohumil Jánský,Vojtěch Rypar,Vlastimil Juříček,Davit Harutyunyan,Martin Schulc,Ján Milčák,Evžen Novák,S. Zaritsky +9 more
TL;DR: In this paper, the authors evaluated the measured neutron flux densities at various VVER-1000 Mock-Up positions by means of comparison with the Monte Carlo simulation, and the effect of the various nuclear data libraries on the calculation results is also studied.
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Comparison of measured and calculated neutron transmission through heavy water for 252Cf source placed in the center of 30 cm diameter sphere
TL;DR: In this paper, measurements and calculations have been made for D 2 O moderated 252 Cf spherical assembly of diameter 30 cm which has been adopted as a calibration standard for the testing of personal neutron dosimeters.
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Validation of differential cross sections by means of 252 Cf spectral averaged cross sections
Martin Schulc,Michal Košťál,Stanislav Simakov,Vojtěch Rypar,Davit Harutyunyan,Jan Šimon,Nicola Burianová,Evžen Novák,Bohumil Jánský,Martin Mareček,Jan Uhlíř +10 more
TL;DR: The presented experimental data can be used to validate nuclear data libraries and reactions used in the practical reactor dosimetry and to specify high energy tail of the 252Cf neutron spectrum.