Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture cross section of natural silicon was recently measured at the Oak Ridge Electron Linear Accelerator (ORELA) in the energy range 1-700 keV. Using the ENDF/B-VI evaluation for initial values, a new evaluation of the resonance parameters was performed by adding the results of the ORELA capture measurements to the experimental database. The computer code SAMMY was used for the analysis of the experimental data; the new version of SAMMY allows accurate calculations of the self-shielding and multiple scattering effects in the capture measurements. The accuracy of the radiative capture widths of the resonances was improved by this analysis. Accurate values of the s-, p- and d-wave neutron strength functions were also obtained. Although the resonance capture component of the present evaluation is 2-3 times smaller than that in ENDF/B-VI, the total capture cross section is much larger, at least for energies >250 keV, because the direct capture component contributes values of the same order of magnitude as the resonance component. The direct component was not taken into account in the ENDF/B-VI evaluation and was calculated for the first time in the present evaluation.
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http://dx.doi.org/10.1093/rpd/nci117 | DOI Listing |
Appl Radiat Isot
February 2025
Nuclear Detection and Instrumentaion Division/Nuclear Reaserch Center of Birine, Djelfa, Algeria.
The combination of experimental measurements and simulations provides valuable insights into the performance and limitations of gamma-ray spectrometry, especially within a specified energy range. This study investigates the impact of cross-section variations on the response of high-purity germanium (HPGe) detectors, focusing on the energy range from 53 keV to 1408 keV. Monte Carlo simulations using the MCNP5 code with two different cross-section libraries, ENDF/B.
View Article and Find Full Text PDFRadiat Prot Dosimetry
January 2023
United States Naval Academy, Mechanical Engineering Department, Annapolis, MD 21402, USA.
The 2018 release of the Evaluated Nuclear Data File (ENDF)/B-VIII.0 library initiated several examinations of the impact of the revised nuclear data on Monte Carlo models. This study used version 6.
View Article and Find Full Text PDFPhys Rev Lett
November 2013
Tulane University, New Orleans, Louisiana 70118, USA.
The most precise determination of the neutron lifetime using the beam method was completed in 2005 and reported a result of τ(n)=(886.3±1.2[stat]±3.
View Article and Find Full Text PDFPhys Med
March 2014
Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, 1477893855 Tehran, Iran.
In this Study characteristics of a new 170Tm brachytherapy seed using thermoluminescent dosimeter and also the Monte Carlo simulations to evaluate between calculated and measured values was determined. Titanium tube contained Tm(NO3)3 powders bombardment at the Tehran Research Reactor (TRR) for a period of 7 days at a flux of 2-3 × 10(13) neutrons/cm2 s. To obtain the radial dose function, g(r), and the anisotropy function, F(r, θ), according to the AAPM TG-43U1 recommendations, 30 cm × 30 cm × 15 cm phantoms of Perspex slabs were used.
View Article and Find Full Text PDFAppl Radiat Isot
October 2008
Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka 590-0494, Japan.
The excitation function for the (63)Cu(n,p)(63)Ni reaction has been measured by activation method using the 4.5 MV Dynamitron accelerator of the Fast Neutron Laboratory of Tohoku University. Copper plates and hollow spherical copper shells were irradiated by neutrons of various energy up to 14.
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