Abstract
The performance of a 7Li(p,n) reaction-based Prompt Gamma Ray Neutron Activation Analysis (PGNAA) setup has been determined for analysis of Portland cement samples using Monte Carlo study. The calculations were carried out for a 7Li(p,n) reaction-based PGNAA setup with an external moderator similar to the one used in a previous 2.8 MeV neutrons-based PGNAA setup. The optimum values of geometry parameters of the 7Li(p,n) reaction-based setup are different from those of the 2.8 MeV neutrons-based setup resulting in better performance of the 7Li(p,n) reaction-based setup. The prompt γ-ray yield from the 7Li(p,n) reaction-based setup is 60-70% higher than that from the 2.8 MeV neutrons-based setup. Although the performances of the 7Li(p,n) reaction-based setup is comparable with that of a previously studied 3H(p,n) reaction-based setup, yet performance of the 7Li(p,n) reaction-based setup is superior to that of the 3H(p,n) reaction-based setup because it has less radiation hazard due to utilization of non-radioactive neutron producing target. This study has provided a theoretical base for experimental test of a 7Li(p,n) reaction-based PGNAA setup.
| Original language | English |
|---|---|
| Pages (from-to) | 411-418 |
| Number of pages | 8 |
| Journal | Applied Radiation and Isotopes |
| Volume | 62 |
| Issue number | 3 |
| DOIs | |
| State | Published - Mar 2005 |
Bibliographical note
Funding Information:The authors wish to acknowledge the support of the Research Institute and Physics Department, King Fahd University of Petroleum and Minerals, Dhahran, Saudi Arabia.
Keywords
- Monte carlo calculations
- Neutrons with maxwellian energy spectrum with kT=25 keV
- PGNAA
- Portland cement sample
ASJC Scopus subject areas
- Radiation