0000000000313216

AUTHOR

M. Dietz

showing 5 related works from this author

Neutron transmission measurements at nELBE

2020

International Conference on Nuclear Data for Science and Technology, ND 2019, Bejing, China, 19 May 2019 - 24 May 2019; The European physical journal / Web of Conferences 239, 01006 (2020). doi:10.1051/epjconf/202023901006

Astrophysics::High Energy Astrophysical PhenomenaQC1-999FluxNeutron transmission53001 natural sciences238UNuclear physicsXe0103 physical sciencesNeutronddc:530High pressure gas010306 general physicsPhysicsHe010308 nuclear & particles physicsNePhysicsOPtnELBE time of flight faciltiyneutron total cross sectionstransmission measurementNatBar (unit)
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New reaction rates for the destruction of $^7$Be during big bang nucleosynthesis measured at CERN/n_TOF and their implications on the cosmological li…

2019

New measurements of the7Be(n,α)4He and7Be(n,p)7Li reaction cross sections from thermal to keV neutron energies have been recently performed at CERN/n_TOF. Based on the new experimental results, astrophysical reaction rates have been derived for both reactions, including a proper evaluation of their uncertainties in the thermal energy range of interest for big bang nucleosynthesis studies. The new estimate of the7Be destruction rate, based on these new results, yields a decrease of the predicted cosmological7Li abundance insufficient to provide a viable solution to the cosmological lithium problem.

PhysicsRange (particle radiation)Large Hadron Collidern_TOF 7Be big bang nucleosynthesis cosmological lithium problem010308 nuclear & particles physicsPhysicsQC1-999chemistry.chemical_element[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]7. Clean energy01 natural sciencesReaction rateNuclear physicsBig Bang nucleosynthesischemistry13. Climate action0103 physical sciencesThermalNeutronLithiumNuclear Physics - Experiment010306 general physicsNuclear Experiment
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Radiative neutron capture on Pu242 in the resonance region at the CERN n_TOF-EAR1 facility

2018

The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with uranium to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. However, an extensive use of MOX fuels, in particular in fast reactors, requires more accurate capture and fission cross sections for some Pu isotopes. In the case of Pu242 there are sizable discrepancies among the existing capture cross-section measurements included in the evaluations (all from the 1970s) resulting in an uncertainty as high as 35% in the fast energy region. Moreover, postirradiation experiments evaluat…

PhysicsNuclear fuelFissile material010308 nuclear & particles physicschemistry.chemical_elementUranium01 natural sciences7. Clean energySpent nuclear fuelNeutron temperatureNuclear physicsNeutron capturechemistry13. Climate action0103 physical sciencesNeutron010306 general physicsMOX fuelPhysical Review C
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Characterization and First Test of an i-TED Prototype at CERN n_TOF

2018

International audience; Neutron capture cross section measurements are of fundamental importance for the study of the slow process of neutron capture, so called s-process. This mechanism is responsible for the formation of most elements heavier than iron in the Universe. To this aim, installations and detectors have been developed, as total energy radiation C$_{6}$ D$_{6}$ detectors. However, these detectors can not distinguish between true capture gamma rays from the sample under study and neutron induced gamma rays produced in the surroundings of the setup. To improve this situation, we propose (Domingo Pardo in Nucl Instr Meth Phys Res A 825:78–86, 2016, [1]) the use of the Compton princ…

PhysicsAstrophysics::High Energy Astrophysical PhenomenaDetectorGamma rayi-TED n_TOF characterizationNeutron radiationRadiation[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]030218 nuclear medicine & medical imagingNuclear physics03 medical and health sciencesNeutron capture0302 clinical medicineNeutron cross sectionNeutronGamma spectroscopy[PHYS.PHYS.PHYS-INS-DET]Physics [physics]/Physics [physics]/Instrumentation and Detectors [physics.ins-det]iTED n_TOF neutron
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Fast-neutron-induced fission cross section of Pu242 measured at the neutron time-of-flight facility nELBE

2019

The fast-neutron-induced fission cross section of $^{242}\mathrm{Pu}$ was measured at the neutron time-of-flight facility $n$ELBE. A parallel-plate fission ionization chamber with novel, homogeneous, large-area $^{242}\mathrm{Pu}$ deposits on Si-wafer backings was used to determine this quantity relative to the IAEA neutron cross-section standard $^{235}\mathrm{U}(n,f)$ in the energy range of 0.5 to 10 MeV. The number of target nuclei was determined from the measured spontaneous fission rate of $^{242}\mathrm{Pu}$. This helps to reduce the influence of the fission fragment detection efficiency on the cross section. Neutron transport simulations performed with geant4, mcnp6, and fluka2011 ar…

Nuclear reactionPhysicsNuclear physicsNeutron transportFissionNuclear TheoryPlutonium-242NeutronNeutron scatteringNuclear ExperimentEnergy (signal processing)Spontaneous fissionPhysical Review C
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