Monte Carlo and analytical models of neutron detection with organic scintillation detectors
Artikel i vetenskaplig tidskrift, 2007

This paper presents a new technique for the analysis of neutron pulse height distributions generated in an organic scintillation detector. The methodology presented can be applied to techniques such as neutron spectrum unfolding, which have a variety of applications, including nuclear nonproliferation and homeland security. The technique is based on two independent approaches: (i) the use of the MCNP-PoliMi code to simulate neutron detection on an event-by-event basis with the Monte Carlo method and (ii) an analytical approach for neutron slowing down and detection processes. We show that the total neutron pulse height response measured by the organic scintillators is given by the sum of a large number of different neutron histories, each composed of a certain number of neutron scatterings on hydrogen and/or carbon. The relative contributions of each of these histories are described for a cylindrical liquid scintillator BC-501A. Simulations and measurements of neutron pulse height distributions are essential for neutron spectrum unfolding procedures. (c) 2007 Elsevier B.V. All rights reserved.

distribution

CALIBRATION

organic scintillator

MCNP CODE

neutron detection

pulse height

MCNP-PoliMi

EFFICIENCY

SPECTROMETRY

Författare

Sara Pozzi

Oak Ridge National Laboratory

M. Flaska

Oak Ridge National Laboratory

Andreas Enqvist

Chalmers, Teknisk fysik, Nukleär teknik

Imre Pazsit

Chalmers, Teknisk fysik, Nukleär teknik

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

0168-9002 (ISSN)

Vol. 582 629-637

Ämneskategorier

Annan teknik

DOI

10.1016/j.nima.2007.08.246