Ústav technické a experimentální fyziky Institute of Experimental and Applied Physics

Microtron MT 25 as a source of neutrons

NázevTitle
Microtron MT 25 as a source of neutronsMicrotron MT 25 as a source of neutrons
Druh výsledkuResult type
Článek v časopiseJournal article
AutořiAuthors
M. Kralik, J. Šolc, D. Chvatil, P. Krist, K. Turek, C. Granja
DOIDOI
10.1063/1.4739404
Časopis / citaceJournal / citation
Review of Scientific Instruments. 2012, 8(83), 1-7. ISSN 0034-6748.
RokYear
2012
JazykLanguage
eng
WoSWoS
000308406500023
ScopusScopus
2-s2.0-84865706891
RIVRIV
RIV/68407700:21670/12:00204153!RIV13-MSM-21670___
ProjektProject
Neutron Facilities in the Czech Republic for Calibration and Testing of ESACompliant Neutron-Sensitive DevicesNeutron Facilities in the Czech Republic for Calibration and Testing of ESACompliant Neutron-Sensitive Devices

AbstraktAbstract

The objective was to describe Microtron MT25 as a source of neutrons generated by bremsstrahlung induced photonuclear reactions in U and Pb targets. Bremsstrahlung photons were produced by electrons accelerated at energy 21.6 MeV. Spectral fluence of the generated neutrons was calculated with MCNPX code and then experimentally determined at two positions by means of a Bonner spheres spectrometer in which the detector of thermal neutrons was replaced by activation Mn tablets or track detectors CR-39 with a B-10 radiator. The measured neutron spectral fluence and the calculated anisotropy served for the estimation of neutron yield from the targets and for the determination of ambient dose equivalent rate at the place of measurement. Microtron MT25 is intended as one of the sources for testing neutron sensitive devices which will be sent into the space

The objective was to describe Microtron MT25 as a source of neutrons generated by bremsstrahlung induced photonuclear reactions in U and Pb targets. Bremsstrahlung photons were produced by electrons accelerated at energy 21.6 MeV. Spectral fluence of the generated neutrons was calculated with MCNPX code and then experimentally determined at two positions by means of a Bonner spheres spectrometer in which the detector of thermal neutrons was replaced by activation Mn tablets or track detectors CR-39 with a B-10 radiator. The measured neutron spectral fluence and the calculated anisotropy served for the estimation of neutron yield from the targets and for the determination of ambient dose equivalent rate at the place of measurement. Microtron MT25 is intended as one of the sources for testing neutron sensitive devices which will be sent into the space