Investigation of Neutron-Production Cross Sections of the Structural Fusion Material 181Ta for (α,xn) Reactions up to 150 MeV Energy

Kaplan, Abdullah

doi:10.1007/s10894-012-9581-x

Cited by 16 publications

(18 citation statements)

References 51 publications

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“…The empirical cross section formula is including proton inelastic cross section and Coulomb effects of reactions induced by proton can be expressed suggested in many studies [9][10][11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26] as follows:…”

Section: Methodsmentioning

confidence: 99%

Particle induced nuclear reaction calculations of Boron target nuclei

et al. 2017

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Abstract.Boron is usable element in many areas such as health, industry and energy. Especially, Boron neutron capture therapy (BNCT) is one of the medical applications. Boron target is irradiated with low energy thermal neutrons and at the end of reactions alpha particles occur. After this process recoiling lithium-7 nuclei is composed. In this study, charge particle induced nuclear reactions calculations of Boron target nuclei were investigated in the incident proton and alpha energy range of 5-50 MeV. The excitation functions for 10 B target nuclei reactions have been calculated by using PCROSS Programming code. The semi-empirical calculations for (p,α) reactions have been done by using cross section formula with new coefficient obtained by Tel et al. The calculated results were compared with the experimental data from the literature.

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Section: Methodsmentioning

confidence: 99%

Particle induced nuclear reaction calculations of Boron target nuclei

et al. 2017

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“…(1). When looping over all possible residual configurations, the multiple preequilibrium contribution is obtained [7][8][9][10][11][12][13][14][15][16][17][18][19][20]. In TALYS, multiple preequilibrium emission is followed up to arbitrary order; though for 96 MeV, only the secondary preequilibrium emission is significant.…”

Section: Tesnat 2016mentioning

confidence: 99%

Theoretical cross sections of tantalum on neutron induced reactions

Siddik

2016

EPJ Web Conf.

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!! Neutron-induced cross-sections for the stable isotope 181 Ta, in the energy region up to 20 MeV have been calculated. Statistical model calculations, based on the Hauser-Feshbach formalism, have been carried out using the TALYS-1.0 and were compared with available experimental data in the literature and with ENDF/B-VII, T = 300 K; JENDL-3.3, T = 300 K and JEFF-3.1, T = 300 K evaluated libraries. ! " !With the advent of fast computers, software that simulates nuclear reactions is able to play an increasingly important role in nuclear data. It is possible to provide an exact computational scheme for sophisticated nuclear models, not only new ones but also those that have been lying on the shelf for decades and only now become amenable for numerical implementation. Large scale comparisons with measurements are within reach. TALYS is a nuclear reaction program created at NRG Petten, the Netherlands, and CEA Bruyères-le-Châtel,France. The purpose of TALYS is to simulate nuclear reactions that involve neutrons, photons, protons, deuterons, tritons, 3 He, and α particles in the 1 keV to 200 MeV energy range. Predicted quantities include integrated, single and double-differential cross sections, for both the continuum and discrete states, residue production and fission cross sections, γ -ray production cross sections, etc. Nuclear cross section data can be obtained by three different ways on the basis of experimental measurement, theoretical model calculations and evaluation data files. Experimental cross section data in the range 15-20 MeV are not available for all neutron induced reactions on Tantalum isotopes however, there is only a limited number of data for at the energy range <15 MeV [1][2][3][4].

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“…Alpha-induced neutron production yield data are required in numerous scenarios including the nuclear fuel cycle [1], nuclear safeguards and forensics [2], geological [3] and astrophysical studies [4], underground facilities [5], nuclear fusion [6] and radiation shielding [7]. In addition to thick-target production yields and neutron energy distributions most applications require small or at least reliable estimates for the uncertainty in the yield data.…”

Section: Introductionmentioning

confidence: 99%

Comparison of thick-target (alpha,n) yield calculation codes

2017

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Abstract. Neutron production yields and energy distributions from (D,n) reactions in light elements were calculated using three different codes (SOURCES, NEDIS and USD) and compared with the existing experimental data in the 3.5-10 MeV alpha energy range. SOURCES and NEDIS display an agreement between calculated and measured yields in the decay series of 235 U, 238 U and 232 Th within r10% for most materials. The discrepancy increases with alpha energy but still an agreement of r20% applies to all materials with reliable elemental production yields (the few exceptions are identified). The calculated neutron energy distributions describe the experimental data, with NEDIS retrieving very well the detailed features. USD generally underestimates the measured yields, in particular for compounds with heavy elements and/or at high alpha energies. The energy distributions exhibit sharp peaks that do not match the observations. These findings may be caused by a poor accounting of the alpha particle energy loss by the code. A big variability was found among the calculated neutron production yields for alphas from Sm decay; the lack of yield measurements for low (~2 MeV) alphas does not allow to conclude on the codes' accuracy in this energy region.

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Investigation of Neutron-Production Cross Sections of the Structural Fusion Material 181Ta for (α,xn) Reactions up to 150 MeV Energy

Cited by 16 publications

References 51 publications

Particle induced nuclear reaction calculations of Boron target nuclei

Particle induced nuclear reaction calculations of Boron target nuclei

Theoretical cross sections of tantalum on neutron induced reactions

Comparison of thick-target (alpha,n) yield calculation codes

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