Search for dissertations about: "neutron multiplicity"
Showing result 1 - 5 of 10 swedish dissertations containing the words neutron multiplicity.
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1. A Fast Pixelated Thermal-Neutron Detector
Abstract : This thesis presents the study of a position-sensitive scintillation-based detector called the Solid-State Neutron Detector (SoNDe). SoNDe is being developed for cold- and thermal-neutron detection at the small-angle neutron scattering (SANS) instrument SKADI at the European Spallation Source (ESS), currently under construction in Lund, Sweden. READ MORE
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2. Neutron Multiplicity Counting with the Analysis of Continuous Detector Signals
Abstract : Neutron multiplicity counting is a non-destructive assay method for determining the mass of fissile materials (primarily plutonium) using the measured values of the singles, doubles and triples detection rates. Traditionally, the detection rates are obtained from the counting statistics of neutron detectors. READ MORE
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3. Studying neutron-induced fission at IGISOL-4 : From neutron source to yield measurements and model comparisons
Abstract : Fission yields represent the probability of producing a certain nuclide in a fission event, and are important observables for fission research. For applications, accurate knowledge of the yields is fundamental at all stages of the fuel cycle of nuclear reactors, e.g., for reactivity calculations, or to estimate (spent) fuel inventory. READ MORE
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4. Nuclear fission and fusion in a random-walk model
Abstract : This dissertation deals with theoretical descriptions of nuclear fission and synthesis of superheavy elements via fusion. The associated shape evolutions are treated using a random-walk approach where both the potential energy and the nuclear level density influence the dynamics. READ MORE
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5. Generalised Campbell formulae for compound Poisson processes with applications in nuclear safeguards
Abstract : Multiplicity counting is a widely used non-destructive assay method for estimating unknown parameters (primarily the mass) of samples of spontaneously fissioning materials (e.g. plutonium). Traditionally, measurements are performed with thermal neutron detectors operating in pulse counting mode. READ MORE