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Characterization of the Graphite Pile as a Source of Thermal Neutrons

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VYKYDAL, Zdeněk, Miloslav KRÁLÍK, Aleš JANČÁŘ, Zdeněk KOPECKÝ, Jan DRESSLER and Martin VEŠKRNA. Characterization of the Graphite Pile as a Source of Thermal Neutrons. 2014.
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Basic information
Original name Characterization of the Graphite Pile as a Source of Thermal Neutrons
Name in Czech Charakteristika grafitového zdroje termálních neutronů
Authors VYKYDAL, Zdeněk (203 Czech Republic), Miloslav KRÁLÍK (203 Czech Republic), Aleš JANČÁŘ (203 Czech Republic), Zdeněk KOPECKÝ (203 Czech Republic), Jan DRESSLER (203 Czech Republic) and Martin VEŠKRNA (203 Czech Republic, guarantor, belonging to the institution).
Edition 2014.
Other information
Original language English
Type of outcome Presentations at conferences
Field of Study Informatics
Country of publisher Czech Republic
Confidentiality degree is not subject to a state or trade secret
RIV identification code RIV/00216224:14330/14:00073300
Organization Fakulta informatiky - Repository
Keywords (in Czech) termální neutrony; He-3 detektor; neutronový zdroj;
Keywords in English graphite pile; thermal neutrons; He-3 detector; neutron source
Links TA01011383, research and development project.
Changed by Changed by: RNDr. Daniel Jakubík, učo 139797. Changed: 1. 9. 2020 22:57.
Abstract
The absorption cross sections of low energy neutrons obey 1/v law for most materials. Therefore, the detection efficiency of a particular detector increase with decreasing neutron energy. Consequently, most of neutron measuring instruments consist of the detector of thermal neutrons which is located inside of the polyethylene moderator. Development of such instruments requires testing and response calibrations in the field of thermal neutrons. Availability of thermal neutron beams on nuclear reactors is limited and access to them is rather complicated, so it is more convenient to moderate neutrons from the radionuclide neutron sources. Since radionuclide neutron sources are producing fast neutrons it is necessary to use an appropriate moderator material like heavy water or graphite to thermalize neutrons from the source and to avoid thermal neutron capture in the same time.
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Poster_IRRMA_CMI_2014.pdf   File version 1. 9. 2020

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Poster_IRRMA_CMI_2014.pdf
Address within IS
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Address for the users outside IS
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Address within Manager for the users outside IS
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Uploaded/Created
Tue 1. 9. 2020 22:57

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  • a concrete person Mgr. Lucie Vařechová, uco 106253
  • a concrete person RNDr. Daniel Jakubík, uco 139797
  • a concrete person Mgr. Jolana Surýnková, uco 220973
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