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(n,2n) and (n,3n) Neutron Induced Reaction Cross Sections above 8 MeV

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Salman H., Ünal R., Oruncak B., Akçaalan U., Yalim H.

Acta Physica Polonica A

2015

vol. 128

issue 2B

B-231-B-235

Neutron induced reaction cross sections for (n,2n) and (n,3n) have been calculated in the energy range between 8 MeV and 26 MeV. Calculations were made for the target nuclei; ^{45}Sc, ^{59}Co, ^{89}Y, ^{93}Nb, ^{103}Rh, ^{169}Tm, ^{175}Lu, ^{181}Ta, ^{197}Au, ^{209}Bi. Calculated results were compared with the available data in EXFOR. Model calculations of present data indicated clearly that some reported data from measurements failed to separate (n,2n) and (n,3n) contributions.

Calculations of (γ,n) Reaction Cross Sections using Different Level Density Models for Some Lanthanide Nuclei

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Akçaalan U., Ünal R., Sarpün İ., Yalim H., Oruncak B.

Acta Physica Polonica A

2015

vol. 128

issue 2B

B-228-B-230

The discrete level information deficiency requires usage of level density models in cross section calculations. The total reaction cross sections for gamma-induced reactions through the six level density models with a consistent parameterization of some lanthanides (^{141}Pr, ^{142}Nd, ^{144}Sm, ^{153}Eu, ^{159}Tb, ^{160}Gd, ^{165}Ho, ^{175}Lu) were calculated using TALYS 1.6 in the incident energy range from 5 to 30 MeV. All calculations from the present study were compared with each other and with data available in the literature.

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2 Acta Physica Polonica A

2 2015

2 Akçaalan U.

2 Oruncak B.

2 Yalim H.

2 Ünal R.

1 Salman H.

1 Sarpün İ.

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(n,2n) and (n,3n) Neutron Induced Reaction Cross Sections above 8 MeV

Calculations of (γ,n) Reaction Cross Sections using Different Level Density Models for Some Lanthanide Nuclei