In this work,differential cross sections ofγ-ray emission produced in nuclear reactions induced by 14.1 MeV neutrons are measured for the 4.439 MeV line from carbon,as well as for 10 individualγ-ray lines from alumi...In this work,differential cross sections ofγ-ray emission produced in nuclear reactions induced by 14.1 MeV neutrons are measured for the 4.439 MeV line from carbon,as well as for 10 individualγ-ray lines from aluminum,6 from silicon,8 from calcium,16 from titanium,6 from chromium,and 14 from iron.The measurements were conducted using the tagged neutron method with four LaBr_(3)(Ce)scintillation detectors positioned at angles of 25°,45°,60°,and 70°relative to the generator target–sample center axis.A neutron generator that can produce 16 separate beams of tagged neutrons was employed,which combined with the detector system,enabled the determination of differential cross-sections for 64 distinct angle values in the range of 17°to 89°.To simplify data visualization,the angular distributions were divided into 5°intervals,with weighted mean values of the angle and differential cross-section calculated for each interval.Corrections for multiple neutron scattering and attenuation,γ-ray attenuation,and total detection efficiency computed using GEANT4 were accounted for in the cross-section calculations.Additional measurements were performed to validate the correction calculations.The totalγ-ray emission cross-sections were obtained by approximating the angular distributions with even-order Legendre polynomial expansions up to the 6th degree,followed by integration over the full solid angle.The total systematic error for the obtained data was estimated as 9.1%.展开更多
文摘In this work,differential cross sections ofγ-ray emission produced in nuclear reactions induced by 14.1 MeV neutrons are measured for the 4.439 MeV line from carbon,as well as for 10 individualγ-ray lines from aluminum,6 from silicon,8 from calcium,16 from titanium,6 from chromium,and 14 from iron.The measurements were conducted using the tagged neutron method with four LaBr_(3)(Ce)scintillation detectors positioned at angles of 25°,45°,60°,and 70°relative to the generator target–sample center axis.A neutron generator that can produce 16 separate beams of tagged neutrons was employed,which combined with the detector system,enabled the determination of differential cross-sections for 64 distinct angle values in the range of 17°to 89°.To simplify data visualization,the angular distributions were divided into 5°intervals,with weighted mean values of the angle and differential cross-section calculated for each interval.Corrections for multiple neutron scattering and attenuation,γ-ray attenuation,and total detection efficiency computed using GEANT4 were accounted for in the cross-section calculations.Additional measurements were performed to validate the correction calculations.The totalγ-ray emission cross-sections were obtained by approximating the angular distributions with even-order Legendre polynomial expansions up to the 6th degree,followed by integration over the full solid angle.The total systematic error for the obtained data was estimated as 9.1%.