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

Author:

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

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.

Publisher

EDP Sciences

Reference6 articles.

1. Linac based photofission inspection system employing novel detection concepts

2. Sibczynski P., Dziedzic A., Grodzicki K., Iwanowska-Hanke J., Moszy´nski M., Swiderski L., Syntfeld-Ka˙zuch A., Wolski D., Carrel F., Grabowski A., Hamel M., Laine F., Sari A., Iovene A., Tintori C., Fontana C., and Pino F., “New perspectives for undoped CaF 2 scintillator as a threshold activation neutron detector” EPJ Web of Conferences, vol. 170, p. 07012, 2018.

3. A fluorocarbon plastic scintillator for neutron detection: Proof of concept

4. Initial MCNP6 Release Overview

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