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Krapivin, M.I.; Matveev, O.A.; Vradij, A.G.; Maslova, L.V.; Khusainov, A.Kh.; Shashurin, V.K.; Yakobson, A.A.
Study into irradiated fuel reprocessing. V. 31977
Study into irradiated fuel reprocessing. V. 31977
AbstractAbstract
[en] Major characteristics of CdTe detectors have been investigated. The gamma detectors av ilable possess an adequate sensitivity and an insufficient energy resolution. To improve the resolution a scheme of pulse selection with respect to their rise times has been used. The scheme provides the energy resolution between 5 and 10 keV for 5 mm3 detectors in the 50-900 keV gamma energy range. As an example an amplitude spectrum of gamma pulses from the mixture of 106Ru, 106Rh, 134Cs, 137Cs, 95Zr and 95Nb isotopes is is presented. A Pu-Be source of fast neutrons with a moderator was used. To investigate the possibility of registering thermal neutrons by the detectors due to neutron radiative capture by 113Cd. The detectors can be used in both spectroscopic and counting modes. Energy resolution, sensitivity and efficiency of such detectors are comparable with those of other thermal neutron detectors. It is pointed out that unlike silicon and germanium based detectors the CdTe detectors with their small dimensions and high efficiency of gamma registration can be used at room temperature without cooling
Original Title
Issledovanie kharakteristik detektorov iz tellurida kadmiya pri registratsii gamma-izlucheniya i teplovykh nejtronov
Source
Sovet Ehkonomicheskoj Vzaimopomoshchi, Moscow (USSR). Postoyanniya Komissiya po Ispol'zovaniyu Atomnoj Ehnergii v Mirnykh Tselyakh; p. 182-187; 1977; p. 182-187; 4. Symposium on study into irradiated fuel reprocessing; Karlovy Vary, Czechoslovakia; 28 Mar - 1 Apr 1977; 4 refs.; 4 figs.; 1 table.
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