Monte Carlo simulation of thermal neutron flux of americium–beryllium source used in neutron activation analysis
| Autor: | Otman Jai, Ahmed Dadouch, Abdessamad Didi, Mohamed Bencheikh |
|---|---|
| Rok vydání: | 2017 |
| Předmět: |
Materials science
010308 nuclear & particles physics Astrophysics::High Energy Astrophysical Phenomena Analytical chemistry General Physics and Astronomy chemistry.chemical_element Flux Americium 01 natural sciences chemistry Heat flux Elemental analysis Neutron flux 0103 physical sciences High Energy Physics::Experiment Neutron Beryllium Neutron activation analysis Nuclear Experiment 010306 general physics |
| Zdroj: | Moscow University Physics Bulletin. 72:460-464 |
| ISSN: | 1934-8460 0027-1349 |
| DOI: | 10.3103/s0027134917050022 |
| Popis: | The neutron activation analysis is a method of exclusively elemental analysis. Its implementation of irradiates the sample which can be analyzed by a high neutron flux, this method is widely used in developed countries with nuclear reactors or accelerators of particle. The purpose of this study is to develop a prototype to increase the neutron flux such as americium–beryllium and have the opportunity to produce radioisotopes. Americium–beryllium is a mobile source of neutron activity of 20 curie, and gives a thermal neutron flux of (1.8 ± 0.0007) × 106 n/cm2 s when using water as moderator, when using the paraffin, the thermal neutron flux increases to (2.2 ± 0.0008) × 106 n/cm2 s, in the case of adding two solid beryllium barriers, the distance between them is 24 cm, parallel and symmetrical about the source, the thermal flux is increased to (2.5 ± 0.0008) × 106 n/cm2 s and in the case of multi-source (6 sources), with-out barriers, increases to (1.17 ± 0.0008) × 107 n/cm2 s with a rate of increase equal to 4.3 and with the both barriers flux increased to (1.37 ± 0.0008) × 107 n/cm2 s. |
| Databáze: | OpenAIRE |
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