In this work a compact system was designed for bulk sample analysis using the technique of PGNAA. The system consists of 252Cf fission neutron source, a moderator/reflector/filter assembly, and a suitable enclosure to delimit the resulting neutron beam. The moderator/reflector/filter arrangement has been optimised to maximise the thermal neutron component useful for samples analysis with a suitably low level of beam contamination. The neutron beam delivered by this compact system is used to irradiate the sample and the prompt gamma rays produced by neutron reactions within the sample elements are detected by appropriate gamma rays detector. Neutron and gamma rays transport calculations have been performed using the Monte Carlo N-Particle transport code (MCNP5).

A Compact Neutron Beam Generator System Designed for Prompt Gamma Nuclear Activation Analysis / J. Ghassoun; D. Mostacci. - In: APPLIED RADIATION AND ISOTOPES. - ISSN 0969-8043. - STAMPA. - 69:8(2011), pp. 1138-1142. [10.1016/j.apradiso.2010.11.014]

A Compact Neutron Beam Generator System Designed for Prompt Gamma Nuclear Activation Analysis

MOSTACCI, DOMIZIANO
2011

Abstract

In this work a compact system was designed for bulk sample analysis using the technique of PGNAA. The system consists of 252Cf fission neutron source, a moderator/reflector/filter assembly, and a suitable enclosure to delimit the resulting neutron beam. The moderator/reflector/filter arrangement has been optimised to maximise the thermal neutron component useful for samples analysis with a suitably low level of beam contamination. The neutron beam delivered by this compact system is used to irradiate the sample and the prompt gamma rays produced by neutron reactions within the sample elements are detected by appropriate gamma rays detector. Neutron and gamma rays transport calculations have been performed using the Monte Carlo N-Particle transport code (MCNP5).
2011
A Compact Neutron Beam Generator System Designed for Prompt Gamma Nuclear Activation Analysis / J. Ghassoun; D. Mostacci. - In: APPLIED RADIATION AND ISOTOPES. - ISSN 0969-8043. - STAMPA. - 69:8(2011), pp. 1138-1142. [10.1016/j.apradiso.2010.11.014]
J. Ghassoun; D. Mostacci
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/92338
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