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Updated: Feb 14, 2026

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Measuring Material Microstructure Under Flow Using 1-2 Plane Flow-Small Angle Neutron Scattering
Published on: February 6, 2014
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CROSS SECTIONS MEASURED BY QUASI-MONOENERGETIC NEUTRONS
Mitja Majerle1, Martin Ansorge1, Pavel Bém1
1Nuclear Physics Institute of the CAS, 250 68 Rež near Prague, Czech Republic.
Radiation Protection Dosimetry
|February 24, 2018
Summary
This study measured neutron reaction cross sections for gold, bismuth, cobalt, iron, and thulium using quasi-monoenergetic neutrons. Results provide crucial data for nuclear applications and reactor dosimetry.
Area of Science:
- Nuclear Physics
- Neutron Activation Analysis
Background:
- Accurate neutron cross-section data is vital for nuclear reactor design, radiation shielding, and nuclear medicine.
- The p+7Li reaction provides a reliable source of quasi-monoenergetic neutrons for experimental studies.
Purpose of the Study:
- To experimentally determine neutron reaction cross sections for several elements (197Au, 209Bi, 59Co, natFe, 169Tm).
- To evaluate neutron energies in the 18-34 MeV range, relevant for advanced nuclear technologies.
Main Methods:
- Irradiation of elemental samples (gold, bismuth, cobalt, natural iron, thulium) with quasi-monoenergetic neutrons.
- Activity measurement using a high-purity germanium (HPGe) detector.
- Calculation of reaction rates and extraction of cross sections using the SAND-II code and the IRDFF database.
Main Results:
- Experimentally determined cross sections for 197Au, 209Bi, 59Co, natFe, and 169Tm were obtained.
- The data covers neutron energies from 18 to 34 MeV, filling gaps in existing nuclear data libraries.
- Comparison with evaluated cross sections from the International Reactor Dosimetry and Fusion File (IRDF) database was performed.
Conclusions:
- The study successfully measured neutron reaction cross sections for key isotopes in a relevant energy range.
- The obtained experimental data can be used to validate and improve nuclear reaction models and evaluated data libraries.
- This research contributes to enhancing the accuracy of nuclear applications, including reactor dosimetry and neutron transport simulations.
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