5,260 research outputs found

    Validation of the SHNC time-dependent transport code based on the spherical harmonics method for complex nuclear fuel assemblies

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    [EN] The diffusion approximation to the time-dependent Boltzmann transport equation gives accurate results for traditional nuclear reactor designs, but new reactor designs and new fuel elements require neutron transport methods. We develop a numerical approximation to the time-dependent transport equation coupled to delayed neutron precursors based on the spherical harmonics P L equations, for odd L, and on the Backward Euler finite difference discretization of time. The resulting scheme can be written as a stationary form of diffusive second order PL equations. This allows a reduction by half to the number of unknowns and also to apply a nodal collocation method to the spatial discretization of the problem, using coarse spatial grids to further reduce memory requirements. This scheme is validated with several transient benchmarks, where the convergence properties are established and compared with the simplified PL approximation. A more realistic transient benchmark, based on the two-group C5 MOX problem, is finally introduced, showing the need of high order P L approximation for complex fuel geometries.This work was partially supported by the Spanish Agencia Estatal de Investigacion under project ENE2017-89029-P-AR, and the Generalitat Valenciana under project PROMETEO/2018/035. The authors express their gratitude to the anonymous reviewers for their suggestions and helpful comments.Capilla Romá, MT.; Talavera Usano, CF.; Ginestar Peiro, D.; Verdú Martín, GJ. (2020). Validation of the SHNC time-dependent transport code based on the spherical harmonics method for complex nuclear fuel assemblies. Journal of Computational and Applied Mathematics. 375:1-21. https://doi.org/10.1016/j.cam.2020.112814S121375McClarren, R. G. (2010). Theoretical Aspects of the SimplifiedPnEquations. Transport Theory and Statistical Physics, 39(2-4), 73-109. doi:10.1080/00411450.2010.535088Capilla, M., Talavera, C. F., Ginestar, D., & Verdú, G. (2005). A nodal collocation method for the calculation of the lambda modes of the PL equations. Annals of Nuclear Energy, 32(17), 1825-1853. doi:10.1016/j.anucene.2005.07.004Capilla, M., Talavera, C. F., Ginestar, D., & Verdú, G. (2012). Application of a nodal collocation approximation for the multidimensional PL equations to the 3D Takeda benchmark problems. Annals of Nuclear Energy, 40(1), 1-13. doi:10.1016/j.anucene.2011.09.014Heizler, S. I. (2010). Asymptotic Telegrapher’s Equation (P1) Approximation for the Transport Equation. Nuclear Science and Engineering, 166(1), 17-35. doi:10.13182/nse09-77Larsen, E. W., Morel, J. E., & McGhee, J. M. (1996). Asymptotic Derivation of the MultigroupP1and SimplifiedPNEquations with Anisotropic Scattering. Nuclear Science and Engineering, 123(3), 328-342. doi:10.13182/nse123-328Frank, M., Klar, A., Larsen, E. W., & Yasuda, S. (2007). Time-dependent simplified PN approximation to the equations of radiative transfer. Journal of Computational Physics, 226(2), 2289-2305. doi:10.1016/j.jcp.2007.07.009Olbrant, E., Larsen, E. W., Frank, M., & Seibold, B. (2013). Asymptotic derivation and numerical investigation of time-dependent simplified equations. Journal of Computational Physics, 238, 315-336. doi:10.1016/j.jcp.2012.10.055B.G. Carlson, G.I. Bell, Solution of the transport equation by the SN method, in: Proc. U.N. Intl. Conf. Peaceful Uses of Atomic Energy, 2nd Geneva P/2386, 1958.Talamo, A. (2013). Numerical solution of the time dependent neutron transport equation by the method of the characteristics. Journal of Computational Physics, 240, 248-267. doi:10.1016/j.jcp.2012.12.020Sjenitzer, B. L., & Hoogenboom, J. E. (2013). Dynamic Monte Carlo Method for Nuclear Reactor Kinetics Calculations. Nuclear Science and Engineering, 175(1), 94-107. doi:10.13182/nse12-44Sjenitzer, B. L., Hoogenboom, J. E., Jiménez Escalante, J., & Sanchez Espinoza, V. (2015). Coupling of dynamic Monte Carlo with thermal-hydraulic feedback. Annals of Nuclear Energy, 76, 27-39. doi:10.1016/j.anucene.2014.09.018Jo, Y., Cho, B., & Cho, N. Z. (2016). Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method. Nuclear Science and Engineering, 183(2), 229-246. doi:10.13182/nse15-100Shaukat, N., Ryu, M., & Shim, H. J. (2017). Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark. Nuclear Engineering and Technology, 49(5), 920-927. doi:10.1016/j.net.2017.04.008Hoffman, A. J., & Lee, J. C. (2016). A time-dependent neutron transport method of characteristics formulation with time derivative propagation. Journal of Computational Physics, 307, 696-714. doi:10.1016/j.jcp.2015.10.039Ginestar, D., Verdú, G., Vidal, V., Bru, R., Marín, J., & Muñoz-Cobo, J. L. (1998). High order backward discretization of the neutron diffusion equation. Annals of Nuclear Energy, 25(1-3), 47-64. doi:10.1016/s0306-4549(97)00046-7Goluoglu, S., & Dodds, H. L. (2001). A Time-Dependent, Three-Dimensional Neutron Transport Methodology. Nuclear Science and Engineering, 139(3), 248-261. doi:10.13182/nse01-a2235Dulla, S., Mund, E. H., & Ravetto, P. (2008). The quasi-static method revisited. Progress in Nuclear Energy, 50(8), 908-920. doi:10.1016/j.pnucene.2008.04.009Miró, R., Ginestar, D., Verdú, G., & Hennig, D. (2002). A nodal modal method for the neutron diffusion equation. Application to BWR instabilities analysis. Annals of Nuclear Energy, 29(10), 1171-1194. doi:10.1016/s0306-4549(01)00103-7Carreño, A., Vidal-Ferràndiz, A., Ginestar, D., & Verdú, G. (2019). Modal methods for the neutron diffusion equation using different spatial modes. Progress in Nuclear Energy, 115, 181-193. doi:10.1016/j.pnucene.2019.03.040Hébert, A. (1987). Development of the nodal collocation method for solving the neutron diffusion equation. Annals of Nuclear Energy, 14(10), 527-541. doi:10.1016/0306-4549(87)90074-0Reed, W. H. (1972). Spherical Harmonic Solutions of the Neutron Transport Equation from Discrete Ordinate Codes. Nuclear Science and Engineering, 49(1), 10-19. doi:10.13182/nse72-a22523Capilla, M., Talavera, C. F., Ginestar, D., & Verdú, G. (2008). A nodal collocation approximation for the multi-dimensional equations – 2D applications. Annals of Nuclear Energy, 35(10), 1820-1830. doi:10.1016/j.anucene.2008.04.008Capilla, M. T., Talavera, C. F., Ginestar, D., & Verdú, G. (2016). Nodal collocation method for the multidimensional PL equations applied to neutron transport source problems. Annals of Nuclear Energy, 87, 89-100. doi:10.1016/j.anucene.2015.07.040Morel, J. E., Adams, B. T., Noh, T., McGhee, J. M., Evans, T. M., & Urbatsch, T. J. (2006). Spatial discretizations for self-adjoint forms of the radiative transfer equations. Journal of Computational Physics, 214(1), 12-40. doi:10.1016/j.jcp.2005.09.017Williams, M. M. R., Welch, J., & Eaton, M. D. (2015). Relationship of the SPN_AN method to the even-parity transport equation. Annals of Nuclear Energy, 81, 342-353. doi:10.1016/j.anucene.2015.03.014Pautz, A., & Birkhofer, A. (2003). DORT-TD: A Transient Neutron Transport Code with Fully Implicit Time Integration. Nuclear Science and Engineering, 145(3), 299-319. doi:10.13182/nse03-a2385Verdú, G., Ginestar, D., Vidal, V., & Muñoz-Cobo, J. L. (1994). 3D λ-modes of the neutron-diffusion equation. Annals of Nuclear Energy, 21(7), 405-421. doi:10.1016/0306-4549(94)90041-8Olson, K. R., & Henderson, D. L. (2004). Numerical benchmark solutions for time-dependent neutral particle transport in one-dimensional homogeneous media using integral transport. Annals of Nuclear Energy, 31(13), 1495-1537. doi:10.1016/j.anucene.2004.04.002Hageman, L. A., & Yasinsky, J. B. (1969). Comparison of Alternating-Direction Time-Differencing Methods with Other Implicit Methods for the Solution of the Neutron Group-Diffusion Equations. Nuclear Science and Engineering, 38(1), 8-32. doi:10.13182/nse38-8Aboanber, A. E., & Hamada, Y. M. (2009). Computation accuracy and efficiency of a power series analytic method for two- and three- space-dependent transient problems. Progress in Nuclear Energy, 51(3), 451-464. doi:10.1016/j.pnucene.2008.10.003Capilla, M., Ginestar, D., & Verdú, G. (2009). Applications of the multidimensional equations to complex fuel assembly problems. Annals of Nuclear Energy, 36(10), 1624-1634. doi:10.1016/j.anucene.2009.08.008Smith, K. S. (1986). Assembly homogenization techniques for light water reactor analysis. Progress in Nuclear Energy, 17(3), 303-335. doi:10.1016/0149-1970(86)90035-1Capilla, M. T., Talavera, C. F., Ginestar, D., & Verdú, G. (2018). Numerical analysis of the 2D C5G7 MOX benchmark using PL equations and a nodal collocation method. Annals of Nuclear Energy, 114, 32-41. doi:10.1016/j.anucene.2017.12.00

    A Finite Difference Representation of Neutrino Radiation Hydrodynamics in Spherically Symmetric General Relativistic Space-Time

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    We present an implicit finite difference representation for general relativistic radiation hydrodynamics in spherical symmetry. Our code, Agile-Boltztran, solves the Boltzmann transport equation for the angular and spectral neutrino distribution functions in self-consistent simulations of stellar core collapse and postbounce evolution. It implements a dynamically adaptive grid in comoving coordinates. Most macroscopically interesting physical quantities are defined by expectation values of the distribution function. We optimize the finite differencing of the microscopic transport equation for a consistent evolution of important expectation values. We test our code in simulations launched from progenitor stars with 13 solar masses and 40 solar masses. ~0.5 s after core collapse and bounce, the protoneutron star in the latter case reaches its maximum mass and collapses further to form a black hole. When the hydrostatic gravitational contraction sets in, we find a transient increase in electron flavor neutrino luminosities due to a change in the accretion rate. The muon- and tauon-neutrino luminosities and rms energies, however, continue to rise because previously shock-heated material with a non-degenerate electron gas starts to replace the cool degenerate material at their production site. We demonstrate this by supplementing the concept of neutrinospheres with a more detailed statistical description of the origin of escaping neutrinos. We compare the evolution of the 13 solar mass progenitor star to simulations with the MGFLD approximation, based on a recently developed flux limiter. We find similar results in the postbounce phase and validate this MGFLD approach for the spherically symmetric case with standard input physics.Comment: reformatted to 63 pages, 24 figures, to be published in ApJ

    A low energy theory for superfluid and solid matter and its application to the neutron star crust

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    We formulate a low energy effective theory describing phases of matter that are both solid and superfluid. These systems simultaneously break translational symmetry and the phase symmetry associated with particle number. The symmetries restrict the combinations of terms that can appear in the effective action and the lowest order terms featuring equal number of derivatives and Goldstone fields are completely specified by the thermodynamic free energy, or equivalently by the long-wavelength limit of static correlation functions in the ground state. We show that the underlying interaction between particles that constitute the lattice and the superfluid gives rise to entrainment, and mixing between the Goldstone modes. As a concrete example we discuss the low energy theory for the inner crust of a neutron star, where a lattice of ionized nuclei coexists with a neutron superfluid.Comment: 21 pages, 1 figur

    Recent developments in mathematical aspects of relativistic fluids

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    We review some recent developments in mathematical aspects of relativistic fluids. The goal is to provide a quick entry point to some research topics of current interest that is accessible to graduate students and researchers from adjacent fields, as well as to researches working on broader aspects of relativistic fluid dynamics interested in its mathematical formalism. Instead of complete proofs, which can be found in the published literature, here we focus on the proofs' main ideas and key concepts. After an introduction to the relativistic Euler equations, we cover the following topics: a new wave-transport formulation of the relativistic Euler equations tailored to applications; the problem of shock formation for relativistic Euler; rough (i.e., low-regularity) solutions to the relativistic Euler equations; the relativistic Euler equations with a physical vacuum boundary; relativistic fluids with viscosity. We finish with a discussion of open problems and future directions of research.Comment: Minor typos correcte

    Numerical Methods for Neutron Transport Calculations of Nuclear Reactors

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    The objective of this thesis, which in clearly inspired by an industrial framework, is to try and narrow the gap between theoretical neutron modelling and application in the context of nuclear reactor design. This thesis is divided into three main chapters, preceded by a general overview. This structure reflects the three main topics which were chosen for this research project. The first topic develops the Spectral Element Method (SEM) approach and its use in conjunction with transport approximations. As it is documented in the specialized numerical analysis handbooks and in previous works by the author, the method has an excellent convergence rate which outperforms most classical schemes, but it has also some important drawbacks which sometimes seem to discourage its use for linear transport problems applied to nontrivial benchmarks. In order to elaborate the methodology of the specific problems encountered in reactor physics, three aspects are addressed looking for improvements. The first topic analyzed is related to the convergence order, whose value is less straightforward to define a priori by means of functional analysis than other numerical schemes. The adjective “spectral” refers in fact to the maximum order claimed, exponential with respect to the average size of the mesh. A comprehensive set of convergence tests is carried out applying SEM to a few transport models and with the aid of manufactured solutions, thus isolating the numerical effects from the deviations which are due only to modelling approximations. The hypothesis of grid conformity is also relaxed, replacing the classical Galerkin variational formulation with the Discontinuous Galerkin theory, characterized by a more flexible treatment of the mesh interfaces; this scheme allows local grid refinement and opens the way, in perspective, to mesh adaption. Finally, a simple and sufficiently flexible technique to deform the boundaries of each mesh is introduced and applied, in order to adapt the grid to curved geometries. In this way, the advantages of SEM can be applied to a vast class of common problems like lattice calculations. Moreover, thanks to a change of the basis functions used in SEM, it is possible to obtain elements with three sides (straight or deformed), that are a typical war horse of the Finite Element approach. The second topic is essentially devoted to the most “industrial” part of the thesis, developed entirely during the stay of the author in the AREVA NP headquarters in Paris. In AREVA, and in all other nuclear engineering enterprises, neutron diffusion is still the preferred neutronic model for full-core studies. Better approximations are reserved for library preparation, fuel studies and code validation, none of these being typically too much time or budget-constrained. Today needs start to require a certain level of improvement also in full-core analyses, trying to fitly model localized dis-homogeneities and reduce the penalizing engineering margins which are taken as provisions. On the other hand, a change in the model does not mean only an effort to write a new code, but has huge follow-ups due to the validation processes required by the authorities. Second-order transport may support the foreseen methodology update because it can be implemented re-using diffusion routines as the computational engine. The AN method, a second-order approximation of the transport equation, has been introduced in some studies, and its effect is discussed. Moreover, some effort has been reserved to the introduction of linear anisotropy in the model. The last topic deals with ray effects; they are a known issue of the discrete ordinate approach (SN methods) which is responsible for a reduction in the accuracy of the solution, especially in penetration problems with low scattering, like several shielding calculations performed for operator safety concerns. Ray effects are here characterized from a formal point of view in both static and time dependent situations. Then, quantitative indicators are defined to help with the interpretation of the SN results. Based on these studies, some mitigation measures are proposed and their efficacy is discussed

    Transient radiative transport in homogeneous/ non-homogeneous participating medium

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    Thermal radiation is important in many applications, and its analysis is difficult in the presence of a participating medium. In traditional engineering studies, the transient term of the radiative transfer equation (RTE) can be neglected. The assumption does not lead to important errors since the temporal variations of the observables e.g. temperature are slow as compared to the time of light of a photon. However in many new applications such as pulsed LASER interaction with materials, the transient effect must be considered in the RTE. In the transient phase, the reflected and the transmitted signals have temporal signatures that persist for a time period greater than the duration of the source pulse. This could be a source of information about the properties field inside the medium. Hence sufficiently accurate solution methods are required. Predicted signals are dependent on the considered models. The results vary significantly from approximate models. In the last few years, the finite volume method (FVM) and discrete transfer method have emerged as one of the most attractive methods for modeling steady state radiative transfer. The present research work deals with the analysis of transient radiative transfer in one dimensional scattering medium using FVM. One boundary is subjected to short pulse irradiation and the other boundary is assumed to be diffused. The effects of short pulse LASER on variation of transmittance and reflectance with time have been observed for a given value of optical thickness and scattering albedo. The results obtained were in accordance with that obtained from the discrete transfer method (DTM)
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