Alpha Induced Reaction Cross Section Calculations of Tantalum Nucleus

Tel, E.; Uğur, F. A.; Gokce, Aisha

doi:10.1007/s10894-012-9550-4

Cited by 11 publications

(1 citation statement)

References 29 publications

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“…In a fusion reactor design, neutron reaction cross-section data are needed and the evaluated values in nuclear data files are generally used for neutronic calculations [7][8][9]. The theoretical nuclear reaction models are usually required to get the prediction of the reaction crosssections, specifically if the experimental data are unavailable or are improbably to be produced because of the experimental troubles [10][11][12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Reaction Cross-Section, Stopping Power and Penetrating Distance Calculations for the Structural Fusion Material 54Fe in Different Reactions

2014

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Nuclear reaction codes give us simplicity to investigate phenomena of nuclear physics. There have many computer programs such as TALYS, EMPIRE, ALICE/ASH, PCROSS, FLUKA and GEANT4. The stopping power of alpha, deuteron, proton and triton in 54 Fe materials is acquired as it has helpful applications of shielding and choosing the proper thickness of the target. Level density is very important to understanding nuclear reaction mechanism. The knowledge of level density for reaction cross-section calculations are required for various application such as astrophysics, accelerator driven subcritical systems, nuclear medicine, fission and fusion reactor design and neutron capture. In this study, we calculated the cross-sections of 54 Fe using TALYS 1.6 and EMPIRE 3.1 codes for different reactions through the four level density models. Stopping powers and penetrating distances were calculated for the alpha, deuteron, proton and triton particles, taking into consideration all possible reactions in 54 Fe for incident energies of 1-45 MeV using GEANT4 calculation code. The obtained reaction crosssection results have been compared with the each other and against the experimental nuclear reaction data existing in EXFOR database.

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