إن العلاقة التحليلية التي تعطي تدفق الحزمة النيوترونية لا تأخذ بعين الاعتبار احتمال
عدم التفكك بالحسبان. في هذا البحث، قمنا باستنتاج العلاقة التحليلية لاحتمال عدم
تفكك النيوترون الحرّ في أثناء عبوره للعينة المراد تحليلها ب NAA. و استنتاج العلاقة
التحليلية لاحتمال عدم أسر النيوترون الحرّ في أثناء عبوره للعينة المراد تحليلها ب
NAA بطريقة أبسط من طريقة الاستنتاج السابقة. و قمنا بإجراء دراسة تطبيقية لمعرفة
تأثير احتمال عدم تفكك النيوترونات الحرة العابرة للعينة على تدفق الحزم النيوترونية
العابرة، من أجل عينة ذات سماكة كبيرة، و من أجل عينات مختلفة و من أجل طاقات
مختلفة للنيوترونات، فتبين أن تأثير احتمال عدم تفكك النيوترون على تدفق الحزمة
النيوترونية لا يمكن أن يكون مهملاً من أجل كافة الطاقات الأعلى من الحرارية.
The analytical relationship that gives the neutron beam flux does
not take into account the probability of decay. In this research, we
concluded the analytical relationship of the probability non decay
of free neutron during the passage of the sample to be analyzed by
NAA. And the conclusion of the analytical relationship to the
probability of non-capture of the free neutron during the its passage
of the sample to be analyzed by NAA in a simpler method than the
previous conclusion. We conducted an application study to
investigate the effect of the probability non decay of free
neutrons, that flowing through sample, On the flux of transient
neutron beam, for neutron beam with various large thickness
samples and for different energies of neutrons. The effect of
probability of neutron decay on neutron beam flux could not be
negligible for all the energies which are bigger than of
thermal.
References used
Hendrik Willem BAAS , Neutron Activation Analysis of Inhomogeneous Large Samples, op maandag 11 oktober 2004 om 13:00 uur
R. Khelifi,1* P. Bode,2 A. Amokrane3, Flux calculation in LSNAA using an 241Am–Be source, Journal of Radioanalytical and Nuclear Chemistry, Vol. 274, No.3 (2007) 639–642
F. Tzika and I. E Stamatelatos, MONTE CARLO SIMULATIONS FOR NON-DESTRUCTIVE ELEMENTAL ANALYSIS OF LARGE SAMPLES BY NEUTRON ACTIVATION ANALYSIS, ,Institute of Nuclear Technology and Radiation Protection, NCSR 'Demokritos', Greece, 11-14 October 2007, Chania, Crete, Greece
The MCNPX and MCNP5-BETA codes were used to simulate the reaction
9Be(p,n)9B in the Syrian cyclotron,to calculate the neutron spectrum emission
from this reaction and for neutronic calculations to design of the thermal
neutron beam for thermal neutron radiography.
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