Search results

1

Calculation of Reaction Cross Sections for Producing Br-75 in the Energy Range of 5-40 MeV

100%

Salman H., Oruncak B., Ünal R.

Acta Physica Polonica A

|

2015

|

vol. 128

|

issue 2B

B-225-B-227

EN

The isotope of bromine, ⁷⁵Br (T_{1/2} = 1.6 h), has a considerable interest in nuclear medicine. The radionuclide ⁷⁵Br is a positron emitter and is useful in positron emission tomography (PET) for fast metabolic processes. In this study the reaction cross sections were calculated for suggested various production mechanisms. The cross sections of charged particle-induced reactions, leading to ⁷⁵Br, were calculated for ⁷⁶Se(p,2n)⁷⁵Br, ⁷⁶Se(d,3n)⁷⁵Br, ⁷⁵As(³He,3n)⁷⁵Br and ⁷⁵As(⁴He,4n)⁷⁵Br using TALYS 1.6. The calculated results are compared with measurement data available in literature. The calculated results indicate that, ⁷⁶Se(p,2n)⁷⁵Br and ⁷⁶Se(d,3n)⁷⁵Br reaction channels have higher cross section values than that of ⁷⁵As(³He,3n)⁷⁵Br reaction channel. Moreover all these reaction channels are in the range of a medium-sized cyclotron.

2

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

88%

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

Acta Physica Polonica A

|

2015

|

vol. 128

|

issue 2B

B-231-B-235

EN

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.

3

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

88%

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

Acta Physica Polonica A

|

2015

|

vol. 128

|

issue 2B

B-228-B-230

EN

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.

Refine search results

3 Acta Physica Polonica A

3 2015

3 Oruncak B.

3 Ünal R.

2 Akçaalan U.

2 Salman H.

2 Yalim H.

1 Sarpün İ.

Calculation of Reaction Cross Sections for Producing Br-75 in the Energy Range of 5-40 MeV

(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