Optimum timing parameters in thermal neutron activation analysis of uranium using delayed neutron counting
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Date
1981-08
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Turkish Atomic Energy Commission
Abstract
Uranyumun gecikmeli nötron sayımına dayanan tekrarlı termal nötron aktivasyon yöntemi ile analizi teorik olarak incelendi. Maksimum dedektör sayımını veren optimum zamanlama parametreleri elde edildi. Bu parametreler, maksimum dedektör sayımının % 95 ve % 90'ı için de araştırıldı. Son olarak, uranyumun adı geçen yöntem ile dedeksiyon limiti üzerinde hesaplamalar yapıldı.
A theoretical treatment of cyclic activation analysis of uranium employing a thermal neutron source and delayed neutron counting is given. Optimum timing parameters for the maximum detector response are obtained. Cycle optimization for 95 % and 90 % of the maximum detector response is also examined. Estimated detection limits based on the realistic values of the thermal neutron flux and detection efficiency are presented.
A theoretical treatment of cyclic activation analysis of uranium employing a thermal neutron source and delayed neutron counting is given. Optimum timing parameters for the maximum detector response are obtained. Cycle optimization for 95 % and 90 % of the maximum detector response is also examined. Estimated detection limits based on the realistic values of the thermal neutron flux and detection efficiency are presented.
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Keywords
Delayed neutron counting, Gecikmeli nötron sayımı, Optimum timing parameters, Optimum zamanlama parametreleri, Uranium, Uranyum, Thermal neutron activation analysis, Termal nötron aktivasyon analizi
Citation
Özek, F. ve Ortaovalı, A. Z. (1981). Optimum timing parameters in thermal neutron activation analysis of uranium using delayed neutron counting. Turkish Journal of Nuclear Sciences, 8(2), 37-42.