Significant work has been performed on the development of STEFF (SpecTrometer for Exotic Fission Fragments), a 2E2V (2-Energy 2-Velocity) spectrometer built by the University of Manchester Fission Group. The majority of this work was in the development of the time-of-flight systems, in particular the stop detector; with the main goals of improving the timing resolution and the detection effciency of the fission fragments. Further development of the STEFF spectrometer was done to enable 2E2V measurements of the 235U(n,f) reaction with coincident measurements using a white neutron spectra of energies ranging from 10 meV to200 MeV provided by the n TOF (neutron Time Of Flight) facility, CERN. The STEFF spectrometer was successfully operated twice on the Experimental Area-2 high flux pulsed neutron beam line resulting in 2E2V measurements for fission events with neutron energies ranging from 20 meV to 10 MeV. The first experiment received 1.36x10^18 POT (Protons On Target) with stable conditions and the second received 1.53x10^18 POT with stable conditions. The development of the stop detector resulted in a replacement MWPC (Multi-Wire Proportional Counter) detector for the second of the two experiments. This allowed direct comparison for the timing coincidence resolution, sigma_c, between the start and stop detectors and gave sigma_c = 0.81+/-0.08 ns for the prior PPAC (Parallel Plate Avalanche Counter) detector and sigma_c = 0.40 +/- 0.04 ns for the MWPC. The MWPC gave improved the detection efficiency per fission fragment of Eff = 0.67 compared to Eff = 0.43 for the PPAC. The methods and research described in this work also provided alternate stop detector designs with greater performance. This work produced two large data sets from the two successful deployments of the STEFF spectrometer on the n TOF beam line that will be the future work of many nuclear structure scientists to come.

Des perspectives énergétiques sobres en carbone pour atténuer le changement climatique nécessitent le remplacement des combustibles fossiles par des sources produisant peu de CO2, par exemple l’énergie nucléaire. L'une des options discutées par le Forum international Gen-IV pour la prochaine génération de réacteurs nucléaires consiste à utiliser le cycle du thorium. L'isotope fissile 233U est l'un des isotopes les plus importants du cycle du thorium et est directement responsable du bilan neutronique. L'une des particularités de ce noyau est d'avoir une section efficace de capture qui est inférieure d'un ordre de grandeur à celle de fission. Cette circonstance rend très difficile la mesure de sa section efficace de capture, comme l'atteste seulement deux jeux de données à haute résolution disponibles depuis les années 1960. Dans cette thèse, une nouvelle mesure auprès de la source de neutrons n_TOF est décrite utilisant une nouvelle chambre à fission compacte insérée au centre d'un détecteur de rayons gamma, le calorimètre à absorption totale. La chambre à fission permet d’identifier et de soustraire les rayons gamma de la réaction de fission dans le but d’améliorer la précision de la section efficace de capture de 233U. La chambre à fission est conçue dans cet objectif. Son excellente performance est décrite en détail et permet d'extraire des informations sur les rayons gamma de fission. Une discussion détaillée du processus de réduction des données et des éléments clés de l’analyse, est présentée et aboutit au calcul du rapport alpha de 233U, le rapport entre la section efficace de capture et celle de fission. / A low-carbon energy outlook to mitigate the climate change requires the replacement of fossil fuel by sources with low CO2 emissions, like nuclear energy.. One of the options discussed in the Gen-IV International Forum for the the next generation of nuclear reactors is to use the thorium cycle. The fissile isotope 233U is among the most important isotopes in the thorium cycle and directly responsible for the neutron economy. One of the particularities of this nucleus is to have a capture cross section which is one order of magnitude lower than fission, making the measurement of the 233U capture cross section very challenging as indicated by only two high resolution data sets available since the 1960s. In this thesis, a new measurement at the n_TOF neutron source is described employing a novel compact fission chamber inserted in the center of the Total Absorption Calorimeter g-ray detector. The fission chamber allows to tag and subsequently subtract the gamma rays from the fission reaction aiming to improve the accuracy of the 233U capture cross section.The performance of the custom tailored fission chamber is described in detail and allows to extract information about the prompt fission g-rays. A detailed discussion of the data reduction process and the key elements in the analysis is given resulting in the calculation of the 233U-alpha-ratio, the ratio between the capture and fission cross-section.