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Toplam kayıt 7, listelenen: 1-7
Comparison of Level Density Models for the Ni-60,Ni-61,Ni-62,Ni-64(p, n) Reactions of Structural Fusion Material Nickel from Threshold to 30 MeV
(Springer, 2015)
The knowledge of level density for reaction cross-section calculations are needed for various applications such as fission and fusion reactor design, accelerator driven sub-critical systems, nuclear medicine, neutron capture ...
Production cross-section calculations of medical P-32, Sn-117, Sm-153 and Re-186,Re-188 radionuclides used in bone pain palliation treatment
(Carl Hanser Verlag, 2015)
In this study, production cross-section calculations of P-32, Sn-117, Sm-153 and Re-186,Re-188 radionuclides used in bone pain palliation treatment produced by Si-30(d,gamma)P-32, Sn-118(gamma,n)Sn-117, Sn-116(n,gamma)Sn-117, ...
Double Differential Cross Section and Stopping Power Calculations of Light Charged Particle Emission for the Structural Fusion Materials Cr-50,Cr-52
(Springer, 2015)
Double differential cross section is a fundamental value to determine nuclear heating and material damages in structural fusion material research. In this study, double differential light charged particle emission cross ...
Double Differential Charged Particle Emission Cross Sections and Stopping Power Calculations for Structural Fusion Materials Ni-58,Ni-60
(Springer, 2015)
In this study, double differential light charged particle emission cross section, which is a fundamental data to determine nuclear heating and material damages in structural fusion material research, for Ni-58,Ni-60 target ...
(γ, 2n)-Reaction cross-section calculations of several even-even lanthanide nuclei using different level density models
(Maik Nauka/Interperiodica/Springer, 2015)
There are several level densitymodels that can be used to predict photo-neutron cross sections. Some of them are Constant Temperature + Fermi GasModel (CTFGM), Back-Shifted Fermi GasModel (BSFM), Generalized Superfluid ...
Neutron Production Cross-Section and Geant4 Calculations of the Structural Fusion Material Co-59 for (alpha,xn) and (gamma,xn) Reactions
(Springer, 2015)
Recent advances in technology and computer sciences give us simplicity to investigate phenomena of nuclear physics. Scientists have improved various nuclear reaction codes such as Talys, Alice/ASH, Cem95, Empire, Geant4 ...
Calculations of Double-Differential Neutron Emission Cross Sections for Be-9 Target Nucleus at 14.2 MeV Neutron Energy
(Springer, 2015)
In this study, we investigated neutron-emission spectra induced by (n,xn) nuclear reactions for the Be-9 structural fusion material at 14.2 MeV neutron energy. We calculated double-differential cross sections () with ...