2 resultados para Dubois, Jules (1862-1928)

em AMS Tesi di Dottorato - Alm@DL - Università di Bologna


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Igor Stravinskij (1882-1971) utilizzò di sovente fonti preesistenti come parte integrante del proprio artigianato compositivo. In questa tesi dottorale ho studiato il processo creativo di Stravinskij negli anni Venti sulle musiche di Pëtr Il'ič Čajkovskij (1840-1893). Nella prima parte della dissertazione ho indagato la Sleeping Princess (1921) e il successivo Mariage d’Aurore (1922-1929), entrambi allestiti dai Ballets russes di Sergej Djagilev (1872-1929). Dopo aver localizzato e contestualizzato le fonti manoscritte e i materiali d’uso, ho ricostruito le ri-orchestrazioni effettuate da Stravinskij della Danse russe (Coda del Pas de deux n. 28) e del Presto del Finale (n. 30), che erano a tutt’oggi inedite. La ricerca sulla Sleeping Princess si è rivelata fondamentale per la conseguente analisi del Baiser de la Fée (1928, Ballets de Mme Ida Rubinstein), balletto basato su pezzi pianistici e romanze per voce e pianoforte di Čajkovskij. Grazie allo studio dello Skizzenbuch VIII, della partitura pianistica manoscritta e di tutte le fonti rinvenute, ho gettato ulteriore luce sul processo compositivo di Stravinskij sulle fonti čajkovskiane. Ho rinvenuto nuove appropriazioni che finora non erano note.

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The objective of this thesis is the power transient analysis concerning experimental devices placed within the reflector of Jules Horowitz Reactor (JHR). Since JHR material testing facility is designed to achieve 100 MW core thermal power, a large reflector hosts fissile material samples that are irradiated up to total relevant power of 3 MW. MADISON devices are expected to attain 130 kW, conversely ADELINE nominal power is of some 60 kW. In addition, MOLFI test samples are envisaged to reach 360 kW for what concerns LEU configuration and up to 650 kW according to HEU frame. Safety issues concern shutdown transients and need particular verifications about thermal power decreasing of these fissile samples with respect to core kinetics, as far as single device reactivity determination is concerned. Calculation model is conceived and applied in order to properly account for different nuclear heating processes and relative time-dependent features of device transients. An innovative methodology is carried out since flux shape modification during control rod insertions is investigated regarding the impact on device power through core-reflector coupling coefficients. In fact, previous methods considering only nominal core-reflector parameters are then improved. Moreover, delayed emissions effect is evaluated about spatial impact on devices of a diffuse in-core delayed neutron source. Delayed gammas transport related to fission products concentration is taken into account through evolution calculations of different fuel compositions in equilibrium cycle. Provided accurate device reactivity control, power transients are then computed for every sample according to envisaged shutdown procedures. Results obtained in this study are aimed at design feedback and reactor management optimization by JHR project team. Moreover, Safety Report is intended to utilize present analysis for improved device characterization.