Dans le cadre des études de neutronique menées pour réacteurs de GEN-IV, les nouveaux outils de calcul des cœurs de réacteur sont implémentés dans l’ensemble du code APOLLO3® pour la partie déterministe. Ces méthodes de calculs s’appuient sur des données nucléaires discrétisée en énergie (appelées multi-groupes et généralement produites par des codes déterministes eux aussi) et doivent être validées et qualifiées par rapport à des calculs basés sur la méthode de référence Monte-Carlo. L’objectif de cette thèse est de mettre au point une technique alternative de production des propriétés nucléaires multi-groupes par un code de Monte-Carlo (TRIPOLI-4®). Dans un premier temps, après avoir réalisé des tests sur les fonctionnalités existantes de l’homogénéisation et de la condensation avec des précisions meilleures accessibles aujourd’hui, des incohérences sont mises en évidence. De nouveaux estimateurs de paramètres multi-groupes ont été développés et validés pour le code TRIPOLI-4®à l’aide de ce code lui-même, puisqu’il dispose de la possibilité d’utiliser ses propres productions de données multi-groupes dans un calcul de cœur. Ensuite, la prise en compte de l’anisotropie de la diffusion nécessaire pour un bon traitement de l’anisotropie introduite par des fuites des neutrons a été étudiée. Une technique de correction de la diagonale de la matrice de la section efficace de transfert par diffusion à l’ordre P1 (nommée technique IGSC et basée sur une évaluation du courant des neutrons par une technique introduite par Todorova) est développée. Une amélioration de la technique IGSC dans la situation où les propriétés matérielles du réacteur changent drastiquement en espace est apportée. La solution est basée sur l’utilisation d’un nouveau courant qui est projeté sur l’axe X et plus représentatif dans la nouvelle situation que celui utilisant les approximations de Todorova, mais valable seulement en géométrie 1D. A la fin, un modèle de fuite B1 homogène est implémenté dans le code TRIPOLI-4® afin de produire des sections efficaces multi-groupes avec un spectre critique calculé avec l’approximation du mode fondamental. Ce modèle de fuite est analysé et validé rigoureusement en comparant avec les autres codes : Serpent et ECCO ; ainsi qu’avec un cas analytique.L’ensemble de ces développements dans TRIPOLI-4® permet de produire des sections efficaces multi-groupes qui peuvent être utilisées dans le code de calcul de cœur SNATCH de la plateforme PARIS. Ce dernier utilise la théorie du transport qui est indispensable pour la nouvelle filière à neutrons rapides. Les principales conclusions sont : -Le code de réseau en Monte-Carlo est une voie intéressante (surtout pour éviter les difficultés de l’autoprotection, de l’anisotropie limitée à un certain ordre du développement en polynômes de Legendre, du traitement des géométries exactes 3D), pour valider les codes déterministes comme ECCO ou APOLLO3® ou pour produire des données pour les codes déterministes ou Monte-Carlo multi-groupes.-Les résultats obtenus pour le moment avec les données produites par TRIPOLI-4® sont comparables mais n’ont pas encore vraiment montré d’avantage par rapport à ceux obtenus avec des données issues de codes déterministes tel qu’ECCO. / In the framework of the Generation IV reactors neutronic research, new core calculation tools are implemented in the code system APOLLO3® for the deterministic part. These calculation methods are based on the discretization concept of nuclear energy data (named multi-group and are generally produced by deterministic codes) and should be validated and qualified with respect to some Monte-Carlo reference calculations. This thesis aims to develop an alternative technique of producing multi-group nuclear properties by a Monte-Carlo code (TRIPOLI-4®).At first, after having tested the existing homogenization and condensation functionalities with better precision obtained nowadays, some inconsistencies are revealed. Several new multi-group parameters estimators are developed and validated for TRIPOLI-4® code with the aid of itself, since it has the possibility to use the multi-group constants in a core calculation.Secondly, the scattering anisotropy effect which is necessary for handling neutron leakage case is studied. A correction technique concerning the diagonal line of the first order moment of the scattering matrix is proposed. This is named the IGSC technique and is based on the usage of an approximate current which is introduced by Todorova. An improvement of this IGSC technique is then presented for the geometries which hold an important heterogeneity property. This improvement uses a more accurate current quantity which is the projection on the abscissa X. The later current can represent the real situation better but is limited to 1D geometries.Finally, a B1 leakage model is implemented in the TRIPOLI-4® code for generating multi-group cross sections with a fundamental mode based critical spectrum. This leakage model is analyzed and validated rigorously by the comparison with other codes: Serpent and ECCO, as well as an analytical case.The whole development work introduced in TRIPLI-4® code allows producing multi-group constants which can then be used in the core calculation solver SNATCH in the PARIS code platform. The latter uses the transport theory which is indispensable for the new generation fast reactors analysis. The principal conclusions are as follows:-The Monte-Carlo assembly calculation code is an interesting way (in the sense of avoiding the difficulties in the self-shielding calculation, the limited order development of anisotropy parameters, the exact 3D geometries) to validate the deterministic codes like ECCO or APOLLO3® and to produce the multi-group constants for deterministic or Monte-Carlo multi-group calculation codes. -The results obtained for the moment with the multi-group constants calculated by TRIPOLI-4 code are comparable with those produced from ECCO, but did not show remarkable advantages.

<p>Neutron-carbon interactions have been studied with a focus on charged-particle production of relevance to radiation protection and medical applications, such as cancer therapy. The measurements have been performed using the particle-detection setup, MEDLEY, and the 96 MeV neutron beam at the The Svedberg Laboratory in Uppsala.</p><p>Double-differential cross sections of inclusive charged-particle production are compared with recent calculations from models based on the GNASH code including direct, preequilibrium and compound processes. For protons, the shapes of the cross-section spectra are reasonably well described by the calculations. For the other particles- <i>d</i>, <i>t</i>, ³He and α- there are important discrepancies, in particular for ³He-ions and α-particles, concerning both shape and magnitude of the spectra.</p><p>Using the new cross sections, partial as well as total KERMA coefficients have been determined. The coefficients have also been compared to previous experimental results and model calculations. The <i>p</i>, <i>d</i> and <i>t</i> KERMA coefficients are in good agreement with those from a previous measurement. For the helium isotopes, there are no previous measurements at this energy. The KERMA coefficients are considerably higher (by up to 30%) than those predicted by the calculations.</p><p>The KERMA results indicate that protons and α -particles are the main contributors to the dose. A 6x6x6 cm³ carbon phantom, exposed to a broad and a pencil-like beam, is used for the computation of the absorbed doses deposited by these two particles in spheres of 1 μm in diameter, located at various positions in the phantom. The maximum doses are deposited at ~3 cm from the surface of neutron impact for protons and within 1 cm for α-particles. For the pencil beam, deposited doses are spread over regions of ~1.5 cm and ~300 μm transverse to the beam for protons and α-particles, respectively. The results are consistent with previous integral measurements at lower energies.</p>

Neutron-carbon interactions have been studied with a focus on charged-particle production of relevance to radiation protection and medical applications, such as cancer therapy. The measurements have been performed using the particle-detection setup, MEDLEY, and the 96 MeV neutron beam at the The Svedberg Laboratory in Uppsala. Double-differential cross sections of inclusive charged-particle production are compared with recent calculations from models based on the GNASH code including direct, preequilibrium and compound processes. For protons, the shapes of the cross-section spectra are reasonably well described by the calculations. For the other particles- d, t, 3He and α- there are important discrepancies, in particular for 3He-ions and α-particles, concerning both shape and magnitude of the spectra. Using the new cross sections, partial as well as total KERMA coefficients have been determined. The coefficients have also been compared to previous experimental results and model calculations. The p, d and t KERMA coefficients are in good agreement with those from a previous measurement. For the helium isotopes, there are no previous measurements at this energy. The KERMA coefficients are considerably higher (by up to 30%) than those predicted by the calculations. The KERMA results indicate that protons and α -particles are the main contributors to the dose. A 6x6x6 cm3 carbon phantom, exposed to a broad and a pencil-like beam, is used for the computation of the absorbed doses deposited by these two particles in spheres of 1 μm in diameter, located at various positions in the phantom. The maximum doses are deposited at ~3 cm from the surface of neutron impact for protons and within 1 cm for α-particles. For the pencil beam, deposited doses are spread over regions of ~1.5 cm and ~300 μm transverse to the beam for protons and α-particles, respectively. The results are consistent with previous integral measurements at lower energies.

Simultaneous measurement of cross sections for pion production in pp recations at beam momenta of 805.2 MeV/c and 796.0 MeV/c with the TOF spectrometer at the COSY accelerator. / Simultane Bestimmung der Wirkungsquerschnitte von pionenproduzierenden pp-Reaktionen bei Strahlimpulsen von 805,2 MeV/c und 796,0 MeV/c mit dem TOF-Spektrometer am Beschleuniger COSY.

No description available.

Als Ladungsbrüten wird die Umwandlung niedrig geladener Ionen, welche über ein breites Spektrum von Elementen bis hin zu exotischen, radioaktiven Spezies erzeugt werden können, in hochgeladene Ionen bezeichnet, was beispielsweise für deren effiziente Nachbeschleunigung oder kern- und atomphysikalische Präzisionsmessungen von Bedeutung ist. In dieser Arbeit wird gezeigt, dass es möglich ist, kompakte, bei Raumtemperatur betriebene Elektronenstrahlionenquellen des Dresden EBIS/T - Typs als Ladungsbrüter zu verwenden. Anhand von Simulationen zum Ioneneinfang sowie Experimenten zur Ioneninjektion und -reextraktion wurden die Ionenquellen Dresden EBIT und EBIS-A als Ladungsbrüter charakterisiert. Eigenschaften der Quellen, welche von besonderem Interesse für das Ladungsbrüten sind, wurden untersucht. Hierzu zählen Elektronenstromdichte, Ionisationsfaktor, Akzeptanz sowie Einfangsbeziehungsweise Brütungseffizienz. An einer Dresden EBIS-A wurden weiterhin die Emittanzen des injizierten und reextrahierten Strahls bestimmt. Neben den Untersuchungen zum Ladungsbrüten selbst wurde dieses als experimentelle Technik für die Bestimmung von Elektronenstoß - Ionisationsquerschnitten der Goldionen Au38+ bis Au46+ bei einer Elektronenenergie von 11,5 keV verwendet. Ein Vergleich der Messwerte mit semiempirisch sowie theoretisch berechneten Daten ergab, dass für die Ionisation der 4d - und 4p - Elektronen von Gold in diesem Energiebereich neben der direkten Stoßionisation auch die Autoionisation nach Elektronenstoß - Anregung in die Betrachtung einbezogen werden muss, um eine gute Übereinstimmung von Theorie und Experiment zu erreichen. / The conversion of low charged ions, which can be produced from a broad spectrum of elements up to exotic, radioactive species, to highly charged ions is called charge breeding, which is an important experimental technique for, e.g., efficient post - acceleration or high - precision nuclear and atomic physics experiments. This work demonstrates the feasibility of charge breeding with compact, room - temperature operated electron beam ion sources of the Dresden EBIS/T type. The sources Dresden EBIT and EBIS-A were characterized as charge breeders by simulations of ion capture as well as ion injection and re-extraction experiments. Properties which are critical for charge breeding, such as electron beam density, ionization factor, acceptance, as well as injection and breeding efficiency, were investigated. Further on, in case of the EBIS-A, emittance studies of the injected as well as re-extracted beam were carried out. In addition to the measurements concentrating on charge breeding itself, this experimental technique was used to measure electron impaction ionization cross sections of gold ions from Au38+ up to Au46+ at an electron energy of 11.5 keV. Comparing the measured values to semi - empirical as well as theoretical calculations, it was found that for the ionization of the 4d and 4p electrons of gold ions in this energy region not only direct electron impact ionization but also excitation - autoionization processes have to be considered in order to achieve a good agreement of theory and experiment.

Thesis (Ph.D.); Submitted to North Carolina State Univ., Raleigh, NC (US); 6 Apr 2005. / Published through the Information Bridge: DOE Scientific and Technical Information. "UCRL-TH-211400" Dashdorj, D. 04/06/2005. Report is also available in paper and microfiche from NTIS.

Doctoral Dissertation, Ph.D., University of California, Berkeley, Berkeley, California, USA. / Published through the Information Bridge: DOE Scientific and Technical Information. "LBNL--56749" Folden III, Charles Marvin. USDOE Director. Office of Science. Office of Nuclear Physics 11/04/2004. Report is also available in paper and microfiche from NTIS.

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