Evaluated gas production cross-section data for natural titanium irradiated with protons at energies up to 3 GeV
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S. Akça
, A. Yu. Konobeyev und U. Fischer
Abstract
Evaluated proton, deuteron, triton, 3He and 4He production cross-section data were prepared for natural titanium irradiated with protons at the energy up to 3 GeV. The evaluated data were obtained from the analysis of results of nuclear model calculations, available measured, and systematic data. The calculations of gas production cross-sections were carried out using the intranuclear cascade model (INC), the pre-equilibrium exciton model, geometry dependence hybrid (GDH) model, Weisskopf-Ewing (WE) model, and the Hauser-Feshbach model. CASCADE, TALYS, ALICE/ASH, and ALICE/HMS codes were used for calculations. Available experimental and systematic data, model calculations were used to evaluate gas production cross-section. The evaluation was carried out using statistical methods implemented in the BEKED code package developed at KIT/INR. The evaluated cross-sections were compared with the data from evaluated data libraries.
Kurzfassung
Produktionswirkungsquerschnitte für Protonen, Deuteronen, Tritonen, 3He- und 4He-Kerne wurden für stabile Titanisotope bei Protonenenergien bis 3 GeV ausgewertet. Die Auswertung wurde mit Hilfe von Modellrechnungen, verfügbaren experimentellen Daten und systematischen Daten durchgeführt. Die Wirkungsquerschnitte für die Gaserzeugung wurden mit Hilfe des intranuklearen Kaskaden-Verdampfungsmodells (INC), des Vorgleichgewichts-Emissions-Modells (PE), des geometrieabhängigen Hybrid-Modells (GDH), des Weisskopf-Ewing-Modells (WE) und des Hauser-Feshbach-Modells (HF) berechnet. Die Rechencodes TALYS, ALICE/ASH, und ALICE/HMS wurden für die numerischen Berechnungen verwendet. Die Auswertung wurde mit Hilfe von statistischen Methoden des am KIT entwickelten BEKED-Programmsystem durchgeführt. Die neu ausgewerteten Wirkungsquerschnitte wurden mit den ausgewerteten Daten von internationalen Bibliotheken verglichen.
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© 2014, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Evaluated gas production cross-section data for natural titanium irradiated with protons at energies up to 3 GeV
- Investigation of (n,γ) reaction in hybrid reactor zones
- Burnup analysis of the VVER-1000 reactor using thorium-based fuel
- Equivalent thermal conductivity of the storage basket with spent nuclear fuel of VVER-1000 reactors
- A study on empirical systematic for the (d,n) reaction cross sections at 8.6 MeV
- Recursive solutions for multi-group neutron kinetics diffusion equations in homogeneous three-dimensional rectangular domains with time dependent perturbations
- Thermoluminescent characteristics of nano-structure hydroxyapatite:Dy
- Performance evaluation of anion exchange resins Purolite NRW-5050 and Duolite A-611 by application of radioisotopic techniques
- A binary mixed integer coded genetic algorithm for multi-objective optimization of nuclear research reactor fuel reloading
- Development of an educational nuclear research reactor simulator
- Technical Notes/Technische Mitteilungen
- Obtaining the neutronic and thermal hydraulic parameters of the VVER-1000 Bushehr nuclear reactor core by coupling nuclear codes
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Evaluated gas production cross-section data for natural titanium irradiated with protons at energies up to 3 GeV
- Investigation of (n,γ) reaction in hybrid reactor zones
- Burnup analysis of the VVER-1000 reactor using thorium-based fuel
- Equivalent thermal conductivity of the storage basket with spent nuclear fuel of VVER-1000 reactors
- A study on empirical systematic for the (d,n) reaction cross sections at 8.6 MeV
- Recursive solutions for multi-group neutron kinetics diffusion equations in homogeneous three-dimensional rectangular domains with time dependent perturbations
- Thermoluminescent characteristics of nano-structure hydroxyapatite:Dy
- Performance evaluation of anion exchange resins Purolite NRW-5050 and Duolite A-611 by application of radioisotopic techniques
- A binary mixed integer coded genetic algorithm for multi-objective optimization of nuclear research reactor fuel reloading
- Development of an educational nuclear research reactor simulator
- Technical Notes/Technische Mitteilungen
- Obtaining the neutronic and thermal hydraulic parameters of the VVER-1000 Bushehr nuclear reactor core by coupling nuclear codes