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The neutron sensitivity of the C6D6 detector setup used at n_TOF facility for capture measurements has been studied by means of detailed GEANT4 simulations. A realistic software replica of the entire n_TOF experimental hall, including the neutron beam line, sample, detector supports and the walls of the experimental area has been implemented in the simulations. The simulations have been analyzed in the same manner as experimental data, in particular by applying the Pulse Height Weighting Technique. The simulations have been validated against a measurement of the neutron background performed with a natC sample, showing an excellent agreement above 1 keV. At lower energies, an additional component in the measured natC yield has been discovered, which prevents the use of natC data for neutron background estimates at neutron energies below a few hundred eV. The origin and time structure of the neutron background have been derived from the simulations. Examples of the neutron background for two different samples are demonstrating the important role of accurate simulations of the neutron background in capture cross-section measurements.
The neutron capture cross section of 58Ni was measured at the neutron time of flight facility n_TOF at CERN, from 27 meV to 400 keV neutron energy. Special care has been taken to identify all the possible sources of background, with the so-called neutron background obtained for the first time using high-precision GEANT4 simulations. The energy range up to 122 keV was treated as the resolved resonance region, where 51 resonances were identified and analyzed by a multilevel R-matrix code SAMMY. Above 122 keV the code SESH was used in analyzing the unresolved resonance region of the capture yield. Maxwellian averaged cross sections were calculated in the temperature range of kT = 5 – 100 keV, and their astrophysical implications were investigated.
To determine the neutron flux in activation experiments, a commonly used monitor is zirconium and in particular the stable isotopes 94,96Zr. 96Zr is very sensitive to epithermal neutrons. Despite its widespread application, most gamma intensities of the radioactive neutron capture product, 97Zr, yield large uncertainties. With the help of a new γ spectroscopy setup and GEANT simulations, we succeeded in determining a new set of γ-ray intensities with significantly reduced uncertainties.
The neutron capture cross section of the s-process branch nucleus 63Ni affects the abundances of other nuclei in its region, especially 63Cu and 64Zn. In order to determine the energy-dependent neutron capture cross section in the astrophysical energy region, an experiment at the Los Alamos National Laboratory has been performed using the calorimetric 4πBaF2 array DANCE. The (n,γ) cross section of 63Ni has been determined relative to the well-known 197Au standard with uncertainties below 15%. Various 63Ni resonances have been identified based on the Q value. Furthermore, the s-process sensitivity of the new values was analyzed with the new network calculation tool NETZ.
Der langsame Neutroneneinfang-Prozess (s-Prozess) ist für die Erzeugung von rund der Hälfte der Elemente zwischen Eisen und Blei verantwortlich. Sein Reaktionspfad enthält entlang des Stabilitätstals einige Verzweigungspunkte an instabilen Isotopen, deren Neutroneneinfangquerschnitte die Produktion schwererer Elemente und deren Isotopen-Verhältnisse beeinflussen. Kennt man ihre Zerfalls- und Neutroneneinfangraten unter den angenommenen stellaren Bedingungen ist es möglich, Rückschlüsse auf die physikalischen Umstände während des s-Prozesses zu ziehen. Einer dieser Verzweigungspunkte ist 63-Ni. Die experimentelle Bestimmung des differentiellen Wirkungsquerschnittes für den Neutroneneinfang an diesem Isotop ist das primäre Ergebnis der vorliegenden Arbeit. Der 63-Ni(n,gamma)- Wirkungsquerschnitt hat Einfluss auf die Häufigkeiten von 64-Ni, die Kupfer- und die Zink-Isotope. Die Sensitivität der Produktion dieser Nuklide in s-Prozess-Szenarien wurde ebenfalls im Rahmen dieser Arbeit anhand von Simulationen des entsprechenden Nukleosynthesenetzwerkes untersucht. Zudem wurde die Datenlage für s-Prozess-Modelle mit einer Flugzeit-Messung des 63-Cu(n,gamma)-Wirkungsquerschnitts erweitert.
Die beiden Experimente zur Querschnittsbestimmung von 63-Ni und 63-Cu fanden am Los Alamos Neutron Science Center in New Mexico, USA statt. Eine aus angereichertem 62-Ni hergestellte 63-Ni-Probe wurde im Rahmen einer Flugzeit-Messung gepulst mit Neutronen bestrahlt. Der Nachweis der prompten Gammastrahlung aufgrund von Neutroneneinfängen erfolgte mit dem 4π-BaF_2-Detektor DANCE. Die kalorimetrische Messung macht den Q-Wert der Reaktion für jedes Einfangereignis zugänglich und erlaubt die Unterscheidung von Ereignissen verschiedener Isotope. Es konnte gezeigt werden, dass diese Methode die Bestimmung von Querschnitten selbst mit Proben ermöglicht, die nur zu einem Bruchteil aus dem zu untersuchenden Isotop bestehen. Der 63-Ni(n,gamma)-Wirkungsquerschnitt wurde für den Energiebereich von 40 eV bis 500 keV mit einer maximalen Unsicherheit von 15% bestimmt. Es zeigte sich, dass theoretische Abschätzungen den Querschnitt bislang um etwa einen Faktor 2 unterschätzten. In demselben Energiebereich konnte der 63-Cu(n,gamma)-Wirkungsquerschnitt mit einer maximalen Unsicherheit von 8% vermessen werden.
The accurate knowledge of the neutron-induced fission cross-sections of actinides and other isotopes involved in the nuclear fuel cycle is essential for the design of advanced nuclear systems, such as Generation-IV nuclear reactors. Such experimental data can also provide the necessary feedback for the adjustment of nuclear model parameters used in the evaluation process, resulting in the further development of nuclear fission models. In the present work, the 240Pu(n,f) cross-section was measured at CERN's n_TOF facility relative to the well-known 235U(n,f) cross section, over a wide range of neutron energies, from meV to almost MeV, using the time-of-flight technique and a set-up based on Micromegas detectors. This measurement was the first experiment to be performed at n_TOF's new experimental area (EAR-2), which offers a significantly higher neutron flux compared to the already existing experimental area (EAR-1). Preliminary results as well as the experimental procedure, including a description of the facility and the data handling and analysis, are presented.
Activations with neutrons in the keV energy range were routinely performed at the Karlsruhe Institute of Technology (KIT) in Germany in order to simulate stellar conditions for neutron-capture cross sections. A quasi-Maxwell-Boltzmann neutron spectrum of kT = 25 keV, being of interest for the astrophysical s-process, was produced by the 7Li(p,n) reaction utilizing a 1912 keV proton beam at the Karlsruhe Van de Graaff accelerator. Activated samples resulting in long-lived nuclear reaction products with half-lives in the order of yr 100 Myr were analyzed by Accelerator Mass Spectrometry (AMS). Comparison of the obtained reaction cross sections to literature data from previous Time-of-Flight (ToF) measurements showed that the selected AMS data are systematically lower than the ToF data. To investigate this discrepancy, 54Fe(n,γ)55Fe and 35Cl(n,γ)36Cl reaction cross sections were newly measured at the Frankfurt Neutron Source (FRANZ) in Germany. To complement the existing data, an additional neutron activation of 54Fe and 35Cl at a proton energy of 2 MeV was performed. The results will give implications for the stellar environment at kT = 90 keV, reaching the not yet experimentally explored high-energy s-process range. AMS measurements of the activated samples are scheduled.
The 33S(n,α)30Si cross section measurement, using 10B(n,α) as reference, at the n_TOF Experimental Area 2 (EAR2) facility at CERN is presented. Data from 0.01 eV to 100 keV are provided and, for the first time, the cross section is measured in the range from 0.01 eV to 10 keV. These data may be used for a future evaluation of the cross section because present evaluations exhibit large discrepancies. The 33S(n,α)30Si reaction is of interest in medical physics because of its possible use as a cooperative target to boron in Neutron Capture Therapy (NCT).
Neutron capture cross sections of unstable isotopes are important for neutron-induced nucleosynthesis as well as for technological applications. A combination of a radioactive beam facility, an ion storage ring and a high flux reactor would allow a direct measurement of neutron induced reactions over a wide energy range on isotopes with half lives down to minutes. The idea is to measure neutron-induced reactions on radioactive ions in inverse kinematics. This means, the radioactive ions will pass through a neutron target. In order to efficiently use the rare nuclides as well as to enhance the luminosity, the exotic nuclides can be stored in an ion storage ring. The neutron target can be the core of a research reactor, where one of the central fuel elements is replaced by the evacuated beam pipe of the storage ring. Using particle detectors and Schottky spectroscopy, most of the important neutron-induced reactions, such as (n,γ), (n,p), (n,α), (n,2n), or (n,f), could be investigated.
We discuss the possibility to build a neutron target for nuclear reaction studies in inverse kinematics utilizing a storage ring and radioactive ion beams. The proposed neutron target is a specially designed spallation target surrounded by a large moderator of heavy water (D2O). We present the resulting neutron spectra and their properties as a target. We discuss possible realizations at different experimental facilities.