VYKYDAL, Zdeněk, Miloslav KRÁLÍK, Aleš JANČÁŘ, Zdeněk KOPECKÝ, Jan DRESSLER and Martin VEŠKRNA. Characterization of the graphite pile as a source of thermal neutrons. Radiation Physics and Chemistry. Elsevier, 2015, vol. 116, November 2015, p. 65-68. ISSN 0969-806X. Available from: https://dx.doi.org/10.1016/j.radphyschem.2015.01.028.
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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 Radiation Physics and Chemistry, Elsevier, 2015, 0969-806X.
Other information
Original language English
Type of outcome Article in a journal
Field of Study 10304 Nuclear physics
Country of publisher United States of America
Confidentiality degree is not subject to a state or trade secret
WWW URL
Impact factor Impact factor: 1.207
RIV identification code RIV/00216224:14330/15:00083306
Organization unit Faculty of Informatics
Doi http://dx.doi.org/10.1016/j.radphyschem.2015.01.028
UT WoS 000362606200013
Keywords (in Czech) Termální neutrony; proporcionální detektor He-3; grafit
Keywords in English Thermal neutrons; Graphite pile; Cadmium ratio; 3He proportional detectors
Tags International impact, Reviewed
Changed by Changed by: RNDr. Pavel Šmerk, Ph.D., učo 3880. Changed: 2/5/2016 06:21.
Abstract
A new graphite pile designed to serve as a standard source of thermal neutrons has been built at the Czech Metrology Institute. Actual dimensions of the pile are 1.95 m (W)×1.95 m (L)×2.0 m (H). At its center, there is a measurement channel whose dimensions are 0.4 m×0.4 m×1.25 m (depth). The channel is equipped with a calibration bench, which allows reproducible placement of the tested/calibrated device. At a distance of 80 cm from the channel axis, six holes are symmetrically located allowing the placement of radionuclide neutron sources of Pu–Be and/or Am–Be type. Spatial distribution of thermal neutron fluence in the cavity was calculated in detail with the MCNP neutron transport code. Experimentally, it was measured with two active detectors: a small 3He proportional detector by the French company LMT, type 0.5 NH 1/1 KF, and a silicon pixel detector Timepix with 10B converter foil. The relative values of thermal neutron fluence rate obtained with active detectors were converted to absolute ones using thermal neutron fluence rates measured by means of gold foil activation. The quality of thermal neutron field was characterized by the cadmium ratio.
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