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

摘要

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~(19)F( n, α )~(16)N threshold activation reaction having neutron energy threshold at 1.6 MeV. As a result, the~(16)N 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.