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The accurate and efficient simulation of coupled neutron-photon problems is necessary for several important radiation detection applications. Examples include the detection of nuclear threats concealed in cargo containers and prompt gamma neutron activation analysis for nondestructive determination of elemental composition of unknown samples. In these applications, high-resolution gamma-ray spectrometers are used to preserve as much information as possible about the emitted photon flux, which consists of both continuum and characteristic gamma rays with discrete energies. Monte Carlo transport is the most commonly used modeling tool for this type of problem, but computational times for many problems can be prohibitive. This work explored the use of coupled Monte Carlo-deterministic methods for the simulation of neutron-induced photons for high-resolution gamma-ray spectroscopy applications. A method was developed for the implementation of coupled neutron-photon problems into RAdiation Detection Scenario Analysis Toolbox (RADSAT), a computer code that couples the complementary strengths of discrete-ordinate and Monte Carlo approaches to obtain high-resolution detector responses. Central to this work was the development of a method for generating multi-group neutron-photon cross-sections in a way that separates the discrete and continuum photon emissions so that the key signatures in neutron activation analysis (i.e., the characteristic line energies) are preserved. The mechanics of the cross-section preparation method are described and contrasted with standard neutron-gamma cross-section sets. These custom cross-sections were then applied to several benchmark problems using the method developed in this work. Multi-group results for neutron and photon flux are compared to MCNP results. Finally, calculated responses of high-resolution spectrometers were compared. The added computational efficiency of the coupled Monte Carlo-deterministic method and the positive agreement achieved in the code-to-code verification make the integration of the coupled neutron-photon method into RADSAT a promising endeavor.

Thesis (Ph.D.); Submitted to Massachusetts Inst. of Tech., Cambridge, MA (US); 1 Sep 2003. / Published through the Information Bridge: DOE Scientific and Technical Information. "JLAB-PHY-03-167" "DOE/ER/40150-2745" Marat Rvachev. 09/01/2003. Report is also available in paper and microfiche from NTIS.

Thesis; Thesis information not provided; 1 Feb 2003. / Published through the Information Bridge: DOE Scientific and Technical Information. "JLAB-PHY-03-38" "DOE/ER/40150-2762" Bin Zhang. 02/01/2003. Report is also available in paper and microfiche from NTIS.

Thesis (M.S. in Physics)--Naval Postgraduate School, January 1965. / Thesis Advisor(s): Handle, Harry E. "January 1965." Description based on title screen as viewed on June 2, 2010 DTIC Descriptor(s): (Neutron Cross Sections, Thermal Neutrons), (Research Reactors, Reactor Feasibility Studies), Fast Neutrons, Gold, Radioactive Isotopes, Measurement, Perturbation Theory, Neutron Capture, Indium, Standards, Errors, Materials, Neutron Flux, Mathematical Analysis, Cadmium, Reactor Shielding Materials, Computer Programming, Foils (Materials), Reactor Control, Reactor Kinetics, Reactor Start Up Sources. DTIC Identifier(s): AGN-201 Reactors Includes bibliographical references (p. 32). Also available in print.

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Dans le cadre de la conception des réacteurs, les schémas de calculs utilisant des codes de cal- culs neutroniques déterministes sont validés par rapport à un calcul stochastique de référence. Les biais résiduels sont dus aux approximations et modélisations (modèle d'autoprotection, développement en polynômes de Legendre des lois de choc) qui sont mises en oeuvre pour représenter les phénomènes physiques (absorption résonnante, anisotropie de diffusion respec- tivement). Ce document se penche sur la question de la pertinence de la modélisation de la loi de choc sur une base polynômiale tronquée. Les polynômes de Legendre sont utilisés pour représenter la section de transfert multigroupe dans les codes déterministes or ces polynômes modélisent mal la forme très piquée de ces sections, surtout dans le cadre des maillages énergétiques fins et pour les noyaux légers. Par ailleurs, cette représentation introduit aussi des valeurs négatives qui n'ont pas de sens physique. Dans ce travail, après une brève description des lois de chocs, les limites des méthodes actuelles sont démontrées. Une modélisation de la loi de choc par une fonction constante par morceaux qui pallie à ces insuffisances, a été retenue. Cette dernière nécessite une autre mod- élisation de la source de transfert, donc une modification de la méthode actuelle des ordonnées discrètes pour résoudre l'équation du transport. La méthode de volumes finis en angle a donc été développée et implantée dans l'environ- nement du solveur Sn Snatch, la plateforme Paris. Il a été vérifié que ses performances étaient similaires à la méthode collocative habituelle pour des sections représentées par des polynômes de Legendre. Par rapport à cette dernière, elle offre l'avantage de traiter les deux représenta- tions des sections de transferts multigroupes : polynômes de Legendre et fonctions constantes par morceaux. Dans le cadre des calculs des réacteurs, cette méthode mixte a été validée sur différents motifs : des cellules en réseau infini, des motifs hétérogènes et un calcul de réflecteur. Les principaux résultats sont : - un développement polynômial à l'ordre P 3 est suffisant par rapport aux biais résiduels dus aux autres modélisations (autoprotection, méthode de résolution spatiale). Cette modéli- sation est convergée au sens de l'anisotropie du choc sur les cas représentatifs des réacteurs à eau légère. - la correction de transport P 0c n'est pas adaptée, notamment sur les calculs d'absorbant B4 C. / In reactor physics, calculation schemes with deterministic codes are validated with respect to a reference Monte Carlo code. The remaining biases are attributed to the approximations and models induced by the multigroup theory (self-shielding models and expansion of the scattering law using Legendre polynomials) to represent physical phenomena (resonant absorption and scattering anisotropy respectively). This work focuses on the relevance of a polynomial expansion to model the scattering law. Since the outset of reactor physics, the latter has been expanded on a truncated Legendre polynomial basis. However, the transfer cross sections are highly anisotropic, with non-zero values for a very small range of the cosine of the scattering angle. Besides, the finer the energy mesh and the lighter the scattering nucleus, the more exacerbated is the peaked shape of this cross section. As such, the Legendre expansion is less suited to represent the scattering law. Furthermore, this model induces negative values which are non-physical. In this work, various scattering laws are briefly described and the limitations of the existing model are pointed out. Hence, piecewise-constant functions have been used to represent the multigroup scattering cross section. This representation requires a different model for the dif- fusion source. The discrete ordinates method which is widely employed to solve the transport equation has been adapted. Thus, the finite volume method for angular discretisation has been developed and imple- mented in Paris environment which hosts the Sn solver, Snatch. The angular finite volume method has been compared to the collocation method with Legendre moments to ensure its proper performance. Moreover, unlike the latter, this method is adapted for both the Legendre moments and the piecewise-constant functions representations of the scattering cross section. This hybrid-source method has been validated for different cases: fuel cell in infinite lattice, heterogeneous clusters and 1D core-reflector calculations. The main results are given below : - a P 3 expansion is sufficient to model the scattering law with respect to the biases due to the other approximations used for calculations (self-shielding, spatial resolution method). This order of expansion is converged for anisotropy representation in the modelling of light water reactors. - the transport correction, P 0c is not suited for calculations, especially for B4 C absorbant.

[pt] Em virtude de sua eficiência, elementos estruturais de paredes finas com seções abertas são comuns em estruturas de aço, sendo secção em I, L, C e T usuais na prática de engenharia. A maior parte das vigas de parede fina tem uma boa resistência à flexão em relação ao eixo principal de inércia, mas uma baixa rigidez à flexão em relação ao eixo de menor inércia e uma baixa rigidez em torção. É por isso que estes elementos apresentam em geral uma instabilidade que leva a um acoplamento de flexo-torção. Muitas destas estruturas trabalham em um regime não linear e uma formulação não linear que leve em conta grandes deslocamentos e os acoplamentos inerentes é necessária. Neste trabalho um modelo não linear para vigas de seção aberta e paredes finas, considerando grandes deslocamentos, os efeitos de encurtamento e acoplamentos em flexão e torção é adotado. Inicialmente um estudo das frequências naturais, das cargas críticas e da relação frequência-carga axial é apresentado para diversos perfis. Com base nestes resultados, faz-se um estudo detalhado do comportamento dinâmico não linear destes perfis destacando o efeito do acoplamento não linear na região de ressonância e sua influência na estabilidade dinâmica da estrutura. Para isto são usadas diversas ferramentas de dinâmica não linear, tais como diagramas de bifurcação, respostas no tempo e plano de fase e bacias de atração. Os resultados mostram que a consideração dos acoplamentos não lineares é essencial para se avaliar o nível de segurança destas estruturas. / [en] Due to its efficiency, thin-walled structural elements with open sections, such as I, L, C and Z profiles, are common in steel structures, being usual in engineering applications. Most thin-walled beams have a good flexural strength around of the principal axis of inertia, but a low one around the axis of lower inertia as well as low torsional stiffness. That is why these elements, generally, show instabilities that lead to flexural torsional coupling. Many of these structures do not work in a linear range and a non-linear formulation that takes into account large displacements and associated couplings is required. This dissertation presents a nonlinear model for extensional beams with thin-walled open section, considering large displacements, and flexural-torsional couplings. Initially a study of the natural frequencies, critical load and axial load vs. frequency relation is presented for different profile kinds. Based on these results, a detailed study of the dynamic behavior of non-linear profiles is made, highlighting the effect of non-linear coupling in the resonance region and its influence on the dynamic stability of the structure. For this, various tools of nonlinear dynamics are used, such as bifurcation diagrams, time histories and phase-space portraits and basins of attraction. The results show that the consideration of non-linear couplings is essential to availed the safety level of these structures.

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Made available in DSpace on 2014-10-09T12:34:46Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:01:16Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP