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Differential cross sections of elastic and inelastic neutron scattering on 93Nb were determined in the energy range from 7.10 MeV to 14.10 MeV at eight incident energies. The data were derived by comparing the net time-of-flight spectra with calculated spectra using a realistic Monte Carlo simulation. The time-of-flight measurement was accompanied by extensive and careful calibrations. PTB-Reihe „Neutronenphysik“ Band PTB-N-56
Differential cross sections of elastic and inelastic neutron scattering on elemental tungsten were determined in the energy range from 7.19 MeV to 14.10 Mev at eight incident energies. The data were derived by comparing the net time-of-flight spectra with calculated spectra using a realistic Monte Carlo simulation. The time-of-flight measurement was accompanied by extensive and careful calibrations. The tungsten cross sections were normalized to hydrogen scattering. The disturbing breakup scattering fraction of the non-monoenergetic DD neutron source can be subtracted after having also been calculated by a Monte Carlo simulation.
Differential cross sections of elastic and inelastic neutron scattering on elemental titanium were determined in the energy range from 7.93 MeV to 14.72 MeV at thirteen incident energies. The data were derived by comparing the net time-of-flight spectra with calculated spectra using a realistic Monte Carlo simulation. The time-of-flight measurement was accompanied by extensive and careful calibrations. The titanium cross sections have been normalized to hydrogen scattering.
In this work, DDX of 51V could be obtained at ten incident energies E0n between 7,99 MeV and 13.90 MeV. This experimental material provides a good basis for testing model calculations because the most important model-invariant parameter „incident engergy“ is varied in a relatively large intervall.
ifferentielle Wirkungsquerschnitte der elastischen und inelastischen Neutronenstreuung an 14N sind im Energiebereich von 7.89 MeV bis 13.85 MeV bei 7 Einschußenergien gemessen worden. Die Kerndaten wurden durch einen Vergleich der gemessenen Netto-Flugzeitspektren mit berechneten abgeleitet, die mittels einer realistischen Monte-Carlo-Simulation erzeugt waren. Die Flugzeitmessung wurde durch umfangreiche und sorgfältige Kalibriermessungen ergänzt. Die an Stickstoff gemessenen Wirkungsquerschnitte sind auf Streuquerschnitte von Wasserstoff normiert. Neben Wirkungsquerschnitten der elastischen Streuung wurden 8 partielle inelastische Querschnitte bei jeder Einschußenergie bestimmt, die zu angeregten Niveaus bzw. einem Dublett von 14N gehören. Durch Anpassung von Legendre-Polynomreihen mit der Methode der kleinsten Quadrate an die gemessenen Winkelverteilungen konnten winkelintegrierte Wirkungsquerschnitte abgeleitet werden. Die Ergebnisse dieser Arbeit sind mit denen anderer Autoren sowie der Evaluation ENDF/B-VI verglichen worden.
Neutron detection efficiencies of NE213 scintillation detectors were determined by comparison of the measured neutron time-of-flight spectrum of a 252Cf source deposited in a parallel-plate, low-mass ionization chamber with its reference neutron energy distribution. Measurement conditions and parameters were systematically varied to study their influence on the efficiencies obtained. The efficiencies derived from the measurement were compared with well-established efficiencies of the detectors used. These efficiencies were calculated with a Monte Carlo code and corrected after comparison with a proton recoil telescope in neutron fluence measurements. Details of the measurement and the data analysis including the corrections needed are discussed.