Cross-Section Calculations on Several Structural Fusion Materials for (γ,3n) Reactions in the Photon Energy Range of 20–110 MeV

Kaplan, Abdullah; Çapalı, Veli

doi:10.1007/s10894-014-9670-0

Cited by 10 publications

(3 citation statements)

References 24 publications

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“…In some studies, only cross sections of photoneutrons and photoprotons have been investigated [3][4][5][6][7][8][9][10][11][12][13][14]. At the same time, theoretical cross sections have been calculated with TALYS 1.6 in some other studies [15][16][17].…”

Section: Introductionmentioning

confidence: 99%

Theoretical Photoneutron Cross Sections and the Effect of Gamma Strength Functions for W, Ag, Nb

Demır

Çetın

2017

Acta Phys. Pol. A

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Section: Introductionmentioning

confidence: 99%

Theoretical Photoneutron Cross Sections and the Effect of Gamma Strength Functions for W, Ag, Nb

Demır

Çetın

2017

Acta Phys. Pol. A

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“…The characteristics of beryllium-oxide have been given in Table 1. For fusion reactor technology and its development; neutron induced reaction cross sections data have a critical importance and evaluated values in nuclear databases form that cross sections are used for neutronic interaction computations [3]. Material analysis is the basis of fission and fusion reactor design and this basis depends on the calculated reaction cross sections.…”

Section: Introductionmentioning

confidence: 99%

Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO

Çapalı

Şekerci

Özdoğan

et al. 2016

SDÜ Fen Bil Enst Der

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BeO is one of the most common moderator material for neutron moderation; due to its high density, neutron capture cross section and physicalchemical properties that provides usage at elevated temperatures. As it's known, for various applications in the field of reactor design and neutron capture, reaction cross-section data are required. The cross-sections of (n,α), (n,2n), (n,t), (n,EL) and (n,TOT) reactions for 9 Be and 16 O nuclei have been calculated by using TALYS 1.6 Two Component Exciton model and EMPIRE 3.2 Exciton model in this study. Hadronic interactions of low energetic neutrons and generated isotopes-particles have been investigated for a situation in which BeO was used as a neutron moderator by using GEANT4, which is a powerful simulation software. In addition, energy deposition along BeO material has been obtained. Results from performed calculations were compared with the experimental nuclear reaction data exist in EXFOR. Özet: BeO; yoğunluğu, nötron yakalama tesir kesiti ve yüksek sıcaklıklarda kullanılmasına imkân veren fiziksel-kimyasal özellikleri sayesinde nötron moderasyonunda oldukça yaygın kullanılan bir moderatör malzemesidir. Bilindiği üzere, reaksiyon tesir kesiti hesaplamaları reaktör tasarımı ve nötron yakalaması alanlarında pek çok çeşitli uygulamalar için gereklidir. Bu çalışmada, 9 Be ve 16 O için (n,α), (n,2n), (n,t), (n,EL) and (n,TOT) reaksiyonları tesir kesiti hesaplamaları TALYS 1.6 İki Bileşenli Eksiton model ve EMPIRE 3.2 Eksiton modelleri kullanılarak tamamlanmıştır. Güçlü bir benzetim programı olan GEANT4 ile BeO'in nötron moderatörü olarak kullanıldığı bir ortam için düşük enerjili nötronların ve üretilen izotop-parçacıkların hadronik etkileri araştırılmıştır. Ek olarak, BeO malzemesi boyunca enerji birikimi elde edilmiştir. Gerçekleştirilen hesaplamaların sonuçları ayrıca EXFOR veri tabanında yer alan deneysel nükleer reaksiyon verileri ile karşılaştırılmıştır. Reaktör Moderator Malzemesi BeO için Nötron Girişli Reaksiyonlarda Reaksiyon

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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

Self Cite

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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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Cross-Section Calculations on Several Structural Fusion Materials for (γ,3n) Reactions in the Photon Energy Range of 20–110 MeV

Cited by 10 publications

References 24 publications

Theoretical Photoneutron Cross Sections and the Effect of Gamma Strength Functions for W, Ag, Nb

Theoretical Photoneutron Cross Sections and the Effect of Gamma Strength Functions for W, Ag, Nb

Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO

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

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