Přehled o publikaci
2014
Characterization of the Graphite Pile as a Source of Thermal Neutrons
VYKYDAL, Zdeněk; Miloslav KRÁLÍK; Aleš JANČÁŘ; Zdeněk KOPECKÝ; Jan DRESSLER et. al.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
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 – 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: 1/9/2020 22:57, RNDr. Daniel Jakubík
Abstract
V originále
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.