Analysis of neutron energy spectrum using indium and lanthanum activation detectors and spectral cover

Analysis of neutron energy spectrum using indium and lanthanum activation detectors and spectral cover

Abstract

Knowledge of the neutron energy spectrum, that is in irradiation channels of new experimental stand, in very important because of the new spectral activation detector development. The Americium-Beryllium neutron source was used for the experimental measurement. The analysis of the neutron energy spectrum was carried out using Indium and Lanthanum activation detectors and spectral covers. The neutron energy spectrum was measured in five irradiation channels using activation and off line gamma ray spectroscopic technique. The thermal neutron spectrum analysis was performed using Indium activation detector and Cadmium and Gadolinium spectral filters. The next analysis was performed using Lanthanum activation detector and cadmium spectral filter. Simulation and calculation of the new experimental stand were carried out using the Monte Carlo method and the MCNP software. Simulation and measurements provided information about thermal neutron fraction in the individual channels. These results are useful for design of next development of advanced spectral cover.

Knowledge of the neutron energy spectrum, that is in irradiation channels of new experimental stand, in very important because of the new spectral activation detector development. The Americium-Beryllium neutron source was used for the experimental measurement. The analysis of the neutron energy spectrum was carried out using Indium and Lanthanum activation detectors and spectral covers. The neutron energy spectrum was measured in five irradiation channels using activation and off line gamma ray spectroscopic technique. The thermal neutron spectrum analysis was performed using Indium activation detector and Cadmium and Gadolinium spectral filters. The next analysis was performed using Lanthanum activation detector and cadmium spectral filter. Simulation and calculation of the new experimental stand were carried out using the Monte Carlo method and the MCNP software. Simulation and measurements provided information about thermal neutron fraction in the individual channels. These results are useful for design of next development of advanced spectral cover.

Neutron spectrum; Spectral indices; Neutron Activation Method

Neutron spectrum; Spectral indices; Neutron Activation Method

VARMUŽA, J.; KATOVSKÝ, K.; ZEMAN, M.; ŠŤASTNÝ, O.

2021

10.10.2017

Physics Department, The Maharaja Sayajirao University of Baroda

Vadodara, India

Proceedings of the ICHERA-2017: international conference on high energy radiation and applications; Vadodara (India); 10-13 Oct 2017

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