Pregled bibliografske jedinice broj: 82332
Selective assessment of fast neutron and gamma components using TLD activation.
Selective assessment of fast neutron and gamma components using TLD activation. // 10th "Tihany" Symposium on Radiation Chemistry - Book of Abstracts
Budimpešta: Hungarian Chemical Society, 2002. str. O-53 (predavanje, međunarodna recenzija, sažetak, znanstveni)
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Naslov
Selective assessment of fast neutron and gamma components using TLD activation.
Autori
Ranogajec-Komor, Maria ; Miljanić, Saveta ; Blagus, Saša ; Knežević, Željka ; Osvay, Margit
Vrsta, podvrsta i kategorija rada
Sažeci sa skupova, sažetak, znanstveni
Izvornik
10th "Tihany" Symposium on Radiation Chemistry - Book of Abstracts
/ - Budimpešta : Hungarian Chemical Society, 2002, O-53
Skup
10th "Tihany" Symposium on Radiation Chemistry
Mjesto i datum
Sopron, Mađarska, 31.08.2002. - 05.09.2002
Vrsta sudjelovanja
Predavanje
Vrsta recenzije
Međunarodna recenzija
Sažetak
In our former study the self induced radioactivity in pure Al2O3 and Al2O3:Mg,Y was investigated using the 27Al(n.a)24Na reaction to measure the neutron part in a mixed n+g irradiation field. A preliminary study was carried out also with high sensitivity Al2O3:C in a 14 MeV neutron field. All these thermoluminescent dosimeters were found suitable for fast neutron dosimetry. The lowest detectable neutron dose was found to be about 300-500 mGy using pure Al2O3 and Al2O3:Mg,Y and about 1 mGy using Al2O3:C. The objectives of the present study were further development of the selective determination of gamma and fast neutron components in a mixed radiation field. To this aim Al2O3:C, Al2O3:Mg,Y and TLD-700 were irradiated with different neutron fluence F in a 14 MeV neutron field. The ratios of the high temperature, LET selective peaks and the “dosimetric” peaks TLD-700 were analysed to determine the fast neutron and gamma component of the radiation field. These results were compared to the secondary TL responses of both types of Al2O3 detectors because they respond only to fast neutrons, and therefore makes it possible to isolate the fast neutron component in a mixed neutron-gamma field. For the determination of the secondary TL response both kinds of Al2O3 detectors were read out after the exposure in order to eliminate any TL induced during irradiation, and than stored for at least 30 hours to undergo self irradiation from 24Na (half life 15.5. hours). In conclusion, fast neutron fluence can be directly measured from the TL induced by the activation of Al2O3 detectors. Combining various detectors, various detectable dose limits can be achieved. Al2O3:C presents a unique sensitivity to gammas and 14 MeV neutrons that could be applicable to mixed neutron-gamma dosimetry.
Izvorni jezik
Engleski
Znanstvena područja
Kemija
POVEZANOST RADA
Projekti:
0098063
Ustanove:
Institut "Ruđer Bošković", Zagreb
Profili:
Željka Knežević Medija
(autor)
Saveta Miljanić
(autor)
Ferencne Ranogajec
(autor)
Saša Blagus
(autor)