Application of fluorine-based threshold activation detector for neutron flux calculation from D-T neutron generator

Paweł Sibczyński; Andrzej Brosławski; Szymon Burakowski; Arkadiusz Chłopik; Marek Dryll; Andrzej Dziedzic; Michał Gierlik; Krystian Grodzicki; Łukasz Kaźmierczak; Tomasz Krakowski; Kamil Niechcielski; Jacek Rzadkiewicz; Ivan Sliphukin; Krystian Trela; Arkadiusz Urban; Kacper Zezuliński; Alessandro Iovene; Carlo Tintori

doi:10.1051/epjconf/202022502004

All issues

Volume 225 (2020)

EPJ Web Conf., 225 (2020) 02004

Abstract

Open Access

Issue		EPJ Web Conf. Volume 225, 2020 ANIMMA 2019 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications


Article Number		02004
Number of page(s)		3
Section		Fusion Diagnostics and Technology
DOI		https://doi.org/10.1051/epjconf/202022502004
Published online		20 January 2020

EPJ Web of Conferences 225, 02004 (2020)
https://doi.org/10.1051/epjconf/202022502004

Application of fluorine-based threshold activation detector for neutron flux calculation from D-T neutron generator

Paweł Sibczyński^*^*, Andrzej Brosławski^*, Szymon Burakowski^*, Arkadiusz Chłopik^*, Marek Dryll^*, Andrzej Dziedzic^*, Michał Gierlik^*, Krystian Grodzicki^*, Łukasz Kaźmierczak^*, Tomasz Krakowski^*, Kamil Niechcielski^*, Jacek Rzadkiewicz^*, Ivan Sliphukin^*, Krystian Trela^*, Arkadiusz Urban^*, Kacper Zezuliński^*, Alessandro Iovene^† and Carlo Tintori^†

^* National Centre for Nuclear Research (NCBJ), Electronics and Detection Systems Division (TJ2), A. Soltana 7, 05-400, Otwock, Poland
^† CAEN S.p.A., Via Vetraia 11, 55049, Viareggio (LU), Italy

Email: pawel.sibczynski@ncbj.gov.pl

Published online: 20 January 2020

Abstract

In this paper we propose a method of fast neutron flux estimation from a pulsed D-T neutron generator with application of single CaF2 scintillation crystal. The analysis method relies on ¹⁹F(n, α)¹⁶N threshold activation reaction having neutron energy threshold at 1.6 MeV. As a result, the ¹⁶N undergo β⁻ decay with half-life of 7.1 s, emitting β particles with endpoint up to 10.4 MeV in the scintillator medium. Integration of the β distribution curve, preceded by calculation of (n, α) rate on F with Monte Carlo N-Particle Transport Code v6 (MCNP6) for fixed geometry, allows to estimate the neutron flux in 4π per second within few minutes.

Key words: neutron detection / Threshold Activation Detection / scintillator / neutron generator

This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

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