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Reactor Perturbation Calculations By Monte Carlo Methods
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Book Synopsis Reactor Perturbation Calculations by Monte Carlo Methods by : M. E. Gubbins
Download or read book Reactor Perturbation Calculations by Monte Carlo Methods written by M. E. Gubbins and published by . This book was released on 1965 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Monte Carlo Particle Transport Methods by : I. Lux
Download or read book Monte Carlo Particle Transport Methods written by I. Lux and published by CRC Press. This book was released on 2018-05-04 with total page 530 pages. Available in PDF, EPUB and Kindle. Book excerpt: With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.
Book Synopsis Monte Carlo Reactor Calculation by : S. Podgor
Download or read book Monte Carlo Reactor Calculation written by S. Podgor and published by . This book was released on 1955 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Monte Carlo Principles and Neutron Transport Problems by : Jerome Spanier
Download or read book Monte Carlo Principles and Neutron Transport Problems written by Jerome Spanier and published by Courier Corporation. This book was released on 2008-01-01 with total page 258 pages. Available in PDF, EPUB and Kindle. Book excerpt: This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques. The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron transport problems. Topics include the computation of thermal neutron fluxes and the superposition principle in resonance escape computations.
Book Synopsis Methods for Including Multiphysics Feedback in Monte Carlo Reactor Physics Calculations by : Matthew Shawn Ellis
Download or read book Methods for Including Multiphysics Feedback in Monte Carlo Reactor Physics Calculations written by Matthew Shawn Ellis and published by . This book was released on 2017 with total page 321 pages. Available in PDF, EPUB and Kindle. Book excerpt: The ability to model and simulate nuclear reactors during steady state and transient conditions is important for designing efficient and safe nuclear power systems. The accurate simulation of a nuclear reactor is particularly challenging because the multiple physical processes within the reactor are tightly coupled, which requires that the numerical methods used to resolve each physical process can accurately and efficiently transfer and utilize data from other applications. Monte Carlo methods are desirable for solving the neutron transport equation required in reactor analysis because of the inherent accuracy of the method, but the Computational Solid Geometry (CSG) representation of the physical geometry makes it difficult to accurately and efficiently perform multiphysics reactor analyses with other applications that utilize finite element or finite volume representations. To address this limitation, a multiphysics coupling framework that minimizes the need for spatial discretization in the Monte Carlo geometry is presented in this thesis. The coupling framework uses Functional Expansion Tallies to transfer multiphysics information from the Monte Carlo application to other multiphysics tools. Additionally, the coupling framework uses a modified method for transporting neutrons through spatially continuous total macroscopic cross section distributions in order to incorporate continuous multiphysics feedback fields such as fuel temperature and coolant density into the Monte Carlo simulation. It has been shown that separable Zernike and Legendre Function Expansion Tallies can effectively reconstruct a continuous distribution of fission power density. Additionally, using a prototypical three-dimensional Light Water Reactor pin cell, the method used to transport neutrons through a continuously varying fuel temperature and coolant density distribution was shown to be 1.7 times faster than a comparable discretized simulation with volume-averaged properties, while still providing a high level of accuracy. Finally, in order to make the overall multiphysics coupling scheme useful for reactor analyses, a novel spatially continuous depletion methodology was developed and investigated. With the spatially continuous depletion methodology, number densities can be represented as a linear combination of polynomials, and those polynomial representations can be integrated through time to predict reactor operation. The spatially continuous depletion methodology was able to accurately predict the eigenvalue and number density distributions in a two-dimensional LWR pin cell depletion containing Gd-157 from a 2 weight percent GdO2 and seven other nuclides in the depletion matrix. Analyses of the spatially continuous depletion methodology showed that significant reductions in the number of tallied values could be achieved if polynomial representations were optimized for each nuclide reaction rate. From the depletion simulations in this thesis, a 23% reduction in the required number of reaction rate tallies compared to a lower-fidelity, 10 radial ring pin discretization was shown to be achievable with nuclide polynomial optimization. In addition to showing potential for reductions in tally memory and computational requirements, the spatially continuous depletion simulation was shown to be equal in computational performance to a discrete simulation with 10 radial rings and 8 azimuthal cuts, while providing a much higher level of spatial fidelity in number density concentrations.
Book Synopsis Monte Carlo Method in Reactor Calculations by : Teodor Roşescu
Download or read book Monte Carlo Method in Reactor Calculations written by Teodor Roşescu and published by . This book was released on 1966 with total page 49 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Investigation of New Estimation Approaches for Nuclear Reactor Computations by Monte Carlo by : Magdi M. H. Ragheb
Download or read book Investigation of New Estimation Approaches for Nuclear Reactor Computations by Monte Carlo written by Magdi M. H. Ragheb and published by . This book was released on 1978 with total page 468 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Method written by and published by . This book was released on 1959 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Monte Carlo Particle Transport Methods by : I. Lux
Download or read book Monte Carlo Particle Transport Methods written by I. Lux and published by CRC Press. This book was released on 2018-05-04 with total page 492 pages. Available in PDF, EPUB and Kindle. Book excerpt: With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.
Book Synopsis Development of a New Monte Carlo Reactor Physics Code by : Jaakko Leppänen
Download or read book Development of a New Monte Carlo Reactor Physics Code written by Jaakko Leppänen and published by . This book was released on 2007 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt: Monte Carlo neutron transport codes are widely used in various reactor physics applications, traditionally related to criticality safety analyses, radiation shielding problems, detector modelling and validation of deterministic transport codes. The main advantage of the method is the capability to model geometry and interaction physics without major approximations. The disadvantage is that the modelling of complicated systems is very computing-intensive, which restricts the applications to some extent. The importance of Monte Carlo calculation is likely to increase in the future, along with the development in computer capacities and parallel calculation. An interesting near-future application for the Monte Carlo method is the generation of input parameters for deterministic reactor simulator codes. These codes are used in coupled LWR full-core analyses and typically based on fewgroup nodal diffusion methods. The input data consists of homogenised fewgroup constants, presently generated using deterministic lattice transport codes. The task is becoming increasingly challenging, along with the development in nuclear technology. Calculations involving high-burnup fuels, advanced MOX technology and next-generation reactor systems are likely to cause problems in the future, if code development cannot keep up with the applications. A potential solution is the use of Monte Carlo based lattice transport codes, which brings all the advantages of the calculation method. So far there has been only a handful of studies on group constant generation using the Monte Carlo method, although the interest has clearly increased during the past few years. The homogenisation of reaction cross sections is simple and straightforward, and it can be carried out using any Monte Carlo code. Some of the parameters, however, require the use of special techniques that are usually not available in general-purpose codes. The main problem is the calculation of neutron diffusion coefficients, which have no continuous-energy counterparts in the Monte Carlo calculation. This study is focused on the development of an entirely new Monte Carlo neutron transport code, specifically intended for reactor physics calculations at the fuel assembly level. The PSG code is developed at VTT Technical Research Centre of Finland and one of the main applications is the generation of homogenised group constants for deterministic reactor simulator codes. The theoretical background on general transport theory, nodal diffusion calculation and the Monte Carlo method are discussed. The basic methodology used in the PSG code is introduced and previous studies related to the topic are briefly reviewed. PSG is validated by comparison to reference results produced by MCNP4C and CASMO-4E in infinite two-dimensional LWR lattice calculations. Group constants generated by PSG are used in ARES reactor simulator calculations and the results compared to reference calculations using CASMO-4E data.
Book Synopsis Monte Carlo Methods for Neutron Flux Calculations in a Pressurized Light Water Power Reactor Using Morse-CG. by : R. A. Lindgren
Download or read book Monte Carlo Methods for Neutron Flux Calculations in a Pressurized Light Water Power Reactor Using Morse-CG. written by R. A. Lindgren and published by . This book was released on 1979 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt: Various methods of optimizing Monte Carlo calculations of fast flux and spectra in a pressurized light water reactor are investigated using the code MORSE. Results in slab and cylindrical geometry are compared with those of the code ANISN. (Author).
Book Synopsis A New Method for Treatment of Uncertainties in Nuclear Reactor Heat Transfer Calculations by : Harry J. Reilly
Download or read book A New Method for Treatment of Uncertainties in Nuclear Reactor Heat Transfer Calculations written by Harry J. Reilly and published by . This book was released on 1969 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1966 with total page 1492 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Physics of High-Temperature Reactors by : Luigi Massimo
Download or read book Physics of High-Temperature Reactors written by Luigi Massimo and published by Elsevier. This book was released on 2013-10-22 with total page 249 pages. Available in PDF, EPUB and Kindle. Book excerpt: Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Book Synopsis Monte Carlo perturbation theory in neutron transport calculations by : M. C. G. Hall
Download or read book Monte Carlo perturbation theory in neutron transport calculations written by M. C. G. Hall and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Monte Carlo Methods and Their Application to Neutron Transport Problems by : Jerome Spanier
Download or read book Monte Carlo Methods and Their Application to Neutron Transport Problems written by Jerome Spanier and published by . This book was released on 1959 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Monte Carlo Calculation of Neutron Heating in a Nuclear Rocket Propellant Tank by : J. R. Streetman
Download or read book A Monte Carlo Calculation of Neutron Heating in a Nuclear Rocket Propellant Tank written by J. R. Streetman and published by . This book was released on 1963 with total page 86 pages. Available in PDF, EPUB and Kindle. Book excerpt: