Neutron capture cross section measurement for the 139La(n,γ)140La reaction at 0.0372 eV
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Naima Belouadah
,
Nadjet Osmani
,
Fatiha Kadem
Abstract
The thermal neutron capture cross section of the 139La(n,γ)140La nuclear reaction at 0.0372 eV energy was measured by the Neutron Diffraction Facility (NDF) in the Es-Salam Nuclear Research Reactor (Algeria). The 197Au(n,γ)198Au reaction was adopted as reference for the Neutron Activation Analysis (NAA). The induced activities in sample and control foils were measured non-destructively by a high-resolution HPGe γ-ray detector. The capture cross section of σ(∼7.5 ± 0.37) b was measured for the first time at this energy after correction for the γ attenuation effect. Our measured value at an energy of 0.0372 eV energy was compared with the evaluated cross sections reported in two different neutron databases, namely ENDF/B-VIII.0 and JENDL-5. The data measured at this energy was extrapolated to the energy 0.0253 eV, assuming 1/ν dependence in the thermal energy region, and the result was compared with the fully measured and evaluated values reported in the literature.
Acknowledgments
The authors would like to express their gratitude to the staff of the Es-Salam Nuclear Research Reactor of Birine (Algeria) for their help in performing irradiations and their cordial help in carrying out experiment.
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Research ethics: Not applicable.
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Informed consent: Not applicable.
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Author contributions: NB: Methodology, Formal analysis, Investigation, Data curation, writing and original draft; NO: Software, Formal analysis, Validation; KB: Formal analysis, Validation; FK: Software, Validation; LY: Software, Validation; MB: Conceptualization, Supervision, NT: Software, Validation; MT: Conceptualization, Supervision.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interest: All authors declare no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
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© 2024 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Original Papers
- Neutron capture cross section measurement for the 139La(n,γ)140La reaction at 0.0372 eV
- Proton and alpha-particle activation studies of natFe, natCu, natTi and natW targets at low energies
- Conversion and characterizations of polypropylene fibers into adsorbent by irradiation, chemically grafting, and their uranium uptake
- Separation of no-carrier-added Bi and stable Bi from thallium
- In vivo evaluation of Cerenkov luminescence and SPECT imaging for nanoscale 177Lu-labeled metal-organic framework
- Radiological hazard assessment of the soil in Daquq district, Kirkuk, Iraq
- Computational study of γ-ray and fast neutron shielding efficacy of (70–x)B2O3 – 5TeO2 – 20SrO – 5ZnO – (x)Bi2O3 glass systems using Phy-X/PSD, XCOM and GEANT-4
- Effect of ZnO particle size on the radiation shielding efficiency of B2O3–BaO–ZnO glass system
Articles in the same Issue
- Frontmatter
- Original Papers
- Neutron capture cross section measurement for the 139La(n,γ)140La reaction at 0.0372 eV
- Proton and alpha-particle activation studies of natFe, natCu, natTi and natW targets at low energies
- Conversion and characterizations of polypropylene fibers into adsorbent by irradiation, chemically grafting, and their uranium uptake
- Separation of no-carrier-added Bi and stable Bi from thallium
- In vivo evaluation of Cerenkov luminescence and SPECT imaging for nanoscale 177Lu-labeled metal-organic framework
- Radiological hazard assessment of the soil in Daquq district, Kirkuk, Iraq
- Computational study of γ-ray and fast neutron shielding efficacy of (70–x)B2O3 – 5TeO2 – 20SrO – 5ZnO – (x)Bi2O3 glass systems using Phy-X/PSD, XCOM and GEANT-4
- Effect of ZnO particle size on the radiation shielding efficiency of B2O3–BaO–ZnO glass system
