Activation cross sections for the (γ,n) reactions on zirconium isotopes

Akkurt, I.; Karpuz, N.; Mavı, B.; Demir, Nilgün

doi:10.1016/j.anucene.2013.10.023

Cited by 7 publications

(5 citation statements)

References 12 publications

(12 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The zirconium is also a potential target for the production of medical isotopes. For this purpose, the cross sections of (γ,n) reaction in nat Zr, 90 Zr, 91 Zr, 92 Zr, 94 Zr and 96 Zr targets have been calculated using the TALYS code [6]. The photonuclear reaction cross sections, especially the photoneutron reaction cross sections, are the fundamental properties of nuclear systems.…”

Section: Introductionmentioning

confidence: 99%

Effect of the Level Density Parameter Ratio on the Cross Sections of Fission of Uranium Isotopes

Karpuz

2016

Acta Phys. Pol. A

View full text Add to dashboard Cite

Nuclear level density is a fission characteristics for each core. Level density parameter ratio a f /an plays an important role in the statistical calculations of the fission, investigation of heavy ion collisions and calculation of the reaction cross sections. In this study, the effects of the different level density ratio on the fission reaction cross section for uranium isotopes were investigated. Calculations were carried out using the Monte Carlo simulation codes ALICE/ASH and TALYS 1.6. The calculated results were compared with the experimental reaction cross sections from literature.

show abstract

Section: Introductionmentioning

confidence: 99%

Effect of the Level Density Parameter Ratio on the Cross Sections of Fission of Uranium Isotopes

Karpuz

2016

Acta Phys. Pol. A

View full text Add to dashboard Cite

show abstract

“…ENDF/B-VII libraries, which are used for theoretical calculations in MCNPX, include nuclear data from 10 −11 to 20 MeV for all isotopes and up to 150 MeV for certain isotopes [8,9]. The data of the ENDF/B-VII and also EXFOR libraries are very important for theoretical calculations [10].…”

Section: Numerical Calculationsmentioning

confidence: 99%

The Effect on Neutronic Calculations of Certain Alternative Fuels in a Boiling Water Reactor by Using MCNPX Monte Carlo Method

2015

View full text Add to dashboard Cite

We were studying on the modeling of boiling water reactor fuel assemblies at pin-by-pin level by using Monte Carlo method. The designed boiling water reactor system is cylinder, and the radius of the cylinder is 228 cm. The total active core height is 315.79 cm. The reactor core was divided into the square lattice 7 × 7 type with a constant pitch of 30 cm. The core was surrounded with the reflector. The reflector was surrounded by SS316LN ferritic steel with width of 3 cm. The mixtures 0.2−1% PuF4 and PuO2 were used as fuel. In this study, the effect on the neutronic calculations of PuF4 and PuO2 fuels was investigated in the designed boiling water reactor system. There were calculated k eff , heat deposition and the fission energy in the designed boiling water reactor system. The three-dimensional (3D) modelling of the reactor core and fuel assembly into the designed boiling water reactor system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B nuclear data library.

show abstract

“…The information on total photonuclear cross sections is, in general, good, since these cross sections are obtainable from the photoneutron cross sections, especially for high atomic number (above copper) elements [3,4].…”

Section: Introductionmentioning

confidence: 99%

Variation of Photoneutron Cross Section with Mass Number

et al. 2015

View full text Add to dashboard Cite

Photonuclear reactions play an important role in many different subfields of nuclear astrophysics, and fields, such as nucleosynthesis applications. The photonuclear reaction cross sections, especially the photoneutron reaction cross sections, are the fundamental properties of nuclear systems. In this study, theoretical evaluation of photoneutron reaction cross sections for 27 ≤ A ≤ 238 targets ( 27 Al, 96 Mo, 181 Ta, 238 U) have been investigated in the incident photon energy range of 7-35 MeV. Monte Carlo code TALYS 1.6 was used to calculate the photoneutron cross sections. The results are compared with the earlier experimental reports in literature and the cross section data in the TENDL-2013 nuclear reaction data library, based on subsequent versions of the TALYS nuclear code system. The photoneutron cross section results and the effects of the mass number of target nuclei are discussed.

show abstract

Activation cross sections for the (γ,n) reactions on zirconium isotopes

Cited by 7 publications

References 12 publications

Effect of the Level Density Parameter Ratio on the Cross Sections of Fission of Uranium Isotopes

Effect of the Level Density Parameter Ratio on the Cross Sections of Fission of Uranium Isotopes

The Effect on Neutronic Calculations of Certain Alternative Fuels in a Boiling Water Reactor by Using MCNPX Monte Carlo Method

Variation of Photoneutron Cross Section with Mass Number

Contact Info

Product

Resources

About