k 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.

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