and disposal. In other cases, gamma-emissions from the activated nucleusmay be too weak in intensity, making it difficult to detect. For theabove reasons H, Li, B, C, N, F, Ne, Si, P, S and Ar are elements thatcannot be detected by delayed TNA, but may be analyzed by the promptgammaemitted as the compound nucleus is de-excited [247]. Moreover,prompt-gamma emission is more suited for on-line and in situ analysis,or when it is not possible to remove the source, or the object, to haltthe activation process and perform analysis for delayed neutrons. Withthe object continuously exposed to neutrons, it will also be difficult todistinguish between gamma-rays produced at different time intervals bythe decay of the activated nuclei. Obviously, prompt activation has alsothe advantage of providing immediate indications. However, neutronactivation performed outside the reactor is not as efficient as that performedwithin the reactor, since a limited neutron flux can be producedusing neutron sources or generators. Also, in prompt analysis, neutronsare absorbed in the surrounding shielding and construction materials,and within the detector itself. This generates a background componentthat interferes with the monitored signal. When it is possible to monitorboth prompt and delayed photon emissions, small concentrationsof almost all elements can be detected, except for oxygen [247]. Oxygenis difficult to monitor with TNA due to its very low thermal-neutronactivation cross-sectionDelayed Thermal-Neutron ActivationDelayed neutron-activation analysis requires removing the tested object(sample) from neutron exposure, so that the emitted delayedgamma-rays can be analyzed independently. The advantage of this approachis that the sample can be analyzed in a low-background area,and counting can be performed for as long as needed to provide an accuratemeasurement. This enables accurate analysis of the interrogatedsample. However, it is neither desirable nor often practical to irradiatea large volume of material, since thermal-neutrons tend to be absorbednear the surface, due to their high cross-section. Moreover, the objectcan remain radioactive for some time due to the delayed emission ofgamma-rays. Therefore, a small sample is commonly used in such analysis,a milligram or less. Such a sample is inserted inside a reactor, or amoderated-neutron assembly (see section 15.3). The efficiency of the activationprocess can be enhanced by cyclic activation, i.e. repeating thecycle of irradiation, delaying and counting, a few times to accumulatean overall increase in the total measured activity [248]. This process is
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