Detailed Information on Publication Record

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 – 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.

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.