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A study has been made of the 90 Zr(n,d) 89 Y reactlion at an incident neutron energy of 22 MeV. The experimental aspect of the study was performed at the Van der Graaf facility at the National Accelerator Centre, using a particle spectrometer developed by K Bharuth-Ram and W R McMurray for the study of neutron-induced charged-particle emissions. The spectrometer, which consists of a telescope of three multiwire proportional counters and a curved plastic scintillator, permits the simultaneous accumulation of data over an angular range of 80°. Solid-angle- calculations have been performed to correct for the effect of the geometry of the system on the angular distribution of the cross-sections. A review has been made of the shell model of the nucleus, the optical potential model and the distorted waves method (or DWBA) for the analysis of direct nuclear reactions. A distorted-waves method analysis of the reaction is performed with the code DWUCK 4 and the resulting angular distribution of the various cross-sections are compared with the experimentally obtained data. ThIs comparison produces spectroscopic factors which are used to perform some analysis of the nuclear structure of the 90 Zr nucleus. / Thesis (M.Sc.)-University of Durban-Westville, 1986.

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Structures were determined for 48 new natural products and several related compounds by NMR methods. One new natural product and two unnatural product structures were determined by X-ray diffraction. Molecular mechanics calculations on two indoles related to the neurotransmitter serotonin and on some synthetic cyclophanes were used to gain information about their preferred conformations. Considerable time is wasted redetermining the structures of known natural products when they are encountered in new sources. To help alleviate this problem, a database which searches on proton NMR chemical shifts was developed.

<p>The increasing demand for characterization of nuclear fuel, both from an operator and authority point of view, motivates the development of new experimental and, preferable, non-destructive methods. In this thesis, some methods based on nuclear spectroscopic techniques are presented.</p><p>Various parameters of irradiated fuel are shown to be determined with high accuracy and confidence by utilizing gamma-ray scanning, tomography and passive neutron assay.</p><p>Specifically, fuel parameters relevant for a secure storage of spent nuclear fuel in a long-term repository, such as e.g. burnup and decay heat, are shown to be determined with adequate accuracy. The techniques developed are expected to be implemented in the planned encapsulation facility in Sweden.</p><p>Also, a device for tomographic measurements of the spatial distribution of thermal power in nuclear fuel assemblies has been built, tested and evaluated. The device utilizes single photon emission computed tomography (SPECT) in order to reconstruct the gamma-ray source distribution within a fuel assembly. The device is expected to be an important tool for validating reactor core simulators regarding new fuel designs.</p><p>For safeguards purposes, two experimental methods for verifying the integrity, i.e. the possible loss of fissile material from a nuclear fuel assembly, are presented. Verification of integrity is shown to be possible on an individual fuel rod level.</p>

The increasing demand for characterization of nuclear fuel, both from an operator and authority point of view, motivates the development of new experimental and, preferable, non-destructive methods. In this thesis, some methods based on nuclear spectroscopic techniques are presented. Various parameters of irradiated fuel are shown to be determined with high accuracy and confidence by utilizing gamma-ray scanning, tomography and passive neutron assay. Specifically, fuel parameters relevant for a secure storage of spent nuclear fuel in a long-term repository, such as e.g. burnup and decay heat, are shown to be determined with adequate accuracy. The techniques developed are expected to be implemented in the planned encapsulation facility in Sweden. Also, a device for tomographic measurements of the spatial distribution of thermal power in nuclear fuel assemblies has been built, tested and evaluated. The device utilizes single photon emission computed tomography (SPECT) in order to reconstruct the gamma-ray source distribution within a fuel assembly. The device is expected to be an important tool for validating reactor core simulators regarding new fuel designs. For safeguards purposes, two experimental methods for verifying the integrity, i.e. the possible loss of fissile material from a nuclear fuel assembly, are presented. Verification of integrity is shown to be possible on an individual fuel rod level.

Im Rahmen der Arbeit wurden Experimente aus den Jahren 2008/09 für die Kerne 86Kr und 136Ba analysiert. Zur Auswertung mussten neben Photonenfluss- und Effizienzbestimmung auch Simulationen durchgeführt werden, welche die experimentellen Bedingungen widerspiegeln. Nicht am Kern gestreute Ereignisse und Detektorantwortfunktionen wurden mit Hilfe des Programmpaketes GEANT4 simuliert, um in den gemessenen Daten berücksichtigt zu werden. Daraus zeigt sich, dass neben diskreten Energiezuständen auch ein beachtlicher Teil des ermittelten Anregungsquerschnitts in einer Art Quasikontinuum aus unauflösbaren Peaks liegt. Die ermittelten Wirkungsquerschnitte werden mit Hilfe eines statistischen Ansatzes auf Verzweigung in mögliche Zerfallskanäle und auf Fütterung durch Zustände höherer Energie korrigiert.