Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
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Md. Shuza Uddin
,
Nazmin Afroze
Abstract
The cross sections of the reaction 98Mo(n, γ)99Mo at neutron energies of 0.0334 eV and 0.0536 eV were measured for the first time using the activation technique, and the resulting values of 116 ± 7 mb and 91 ± 5 mb, respectively, are in good agreement with the JENDL-4 and ENDF/B-VII data files. Those measured values were extrapolated to the energy 0.0253 eV assuming 1/v dependence in the thermal region and the results were compared with the integrally measured values reported in the literature. The new data are thus useful to check the evaluated excitation function.
Acknowledgement
The authors thank the Director, Reactor Operation and Maintenance Unit (ROMU) and reactor operation crew for their help in performing irradiations. The authors are highly grateful to T.K. Datta and other scientists and staff of the RNPD and TAFD of the Institute of Nuclear Science and Technology for their cordial advice in carrying out this research. The authors gratefully acknowledge Prof. Dr. S.M. Qaim of Research Center Juelich, Germany for guidance to properly present this work.
©2015 Walter de Gruyter Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
