研究目的
To develop and validate methods for obtaining the net peak count of characteristic c-rays from interlaced overlap peaks in HPGe c-ray spectrometer systems, addressing limitations in current software for complex spectra in nuclear reaction cross-section measurements, neutron activation analysis, and transuranium element analysis.
研究成果
The study successfully developed and validated two methods for obtaining reliable net peak counts from interlaced overlap peaks in HPGe c-ray spectra. The symmetric conversion method based on Gaussian distribution is effective for small overlaps, while the energy average method is suitable for significant overlaps from the same reaction. Experimental results showed consistency with literature and evaluated data, confirming the methods' reliability. This work supports the development of improved c-ray spectrum processing software for applications in nuclear physics, enhancing accuracy in cross-section measurements, neutron activation analysis, and transuranium element analysis. Future research could extend these methods to other types of spectral interferences or integrate them into automated software tools.
研究不足
The methods are specific to interlaced overlap peaks in c-ray spectra and may not be applicable to other types of spectral overlaps or detectors. The energy average method is only valid when overlapping c-rays originate from the same nuclear reaction. Experimental conditions, such as neutron energy and sample purity, could affect results, and further optimization might be needed for different spectrometer systems or lower signal-to-noise ratios.
1:Experimental Design and Method Selection:
The study designed experiments to test two new methods for processing interlaced overlap peaks in c-ray spectra: a symmetric conversion method based on Gaussian distribution for small overlaps and an energy average method for significant overlaps from the same reaction. The rationale was to overcome the inability of existing HPGe multichannel spectrum software to provide reliable net counts in such cases.
2:Sample Selection and Data Sources:
Samples included natural tungsten foils (purity 99.99%, thickness 2.0 mm, diameter 2.0 cm) irradiated with 14 MeV neutrons from a T(d,n)4He reaction at the K-400 Neutron Generator. Data were collected using a calibrated HPGe detector, with decay characteristics and abundances referenced from standard nuclear data sources (e.g., NuDat 2.6, Table of Isotopes).
3:99%, thickness 0 mm, diameter 0 cm) irradiated with 14 MeV neutrons from a T(d,n)4He reaction at the K-400 Neutron Generator. Data were collected using a calibrated HPGe detector, with decay characteristics and abundances referenced from standard nuclear data sources (e.g., NuDat 6, Table of Isotopes).
List of Experimental Equipment and Materials:
3. List of Experimental Equipment and Materials: Equipment: K-400 Neutron Generator (Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics), GEM-60P coaxial HPGe detector (crystal diameter
4:1 mm, length 3 mm, relative efficiency ~68%, energy resolution ~69 keV FWHM at 33 MeV), standard c sources for calibration. Materials:
Natural tungsten foils, niobium disks (purity >99.99%, thickness 1.0 mm), cadmium foil (purity >99.95%, thickness 1.0 mm).
5:99%, thickness 0 mm), cadmium foil (purity >95%, thickness 0 mm).
Experimental Procedures and Operational Workflow:
4. Experimental Procedures and Operational Workflow: Samples were irradiated at specific angles and distances from the neutron source, monitored for neutron flux using alpha-particles. After irradiation, c-activities were measured with the HPGe detector. Spectra were analyzed using the proposed methods: for small overlaps, the symmetric conversion method was applied to calculate net counts; for significant overlaps, the energy average method was used. Background counts were subtracted using predefined methods, and cross sections were calculated relative to a monitor reaction (93Nb(n,2n)92mNb).
6:Data Analysis Methods:
Data analysis involved calculating net peak counts using the symmetric conversion and energy average methods. Cross sections were computed using an equation from literature, with statistical uncertainties considered. Results were compared with literature values and evaluated nuclear data (JEFF-3.3, JENDL-4.0) to validate reliability.
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