Deterministic Numerical Methods For Unstructured Mesh Neutron Transport Calculation

Author : Liangzhi Cao
Publisher : Woodhead Publishing
ISBN 13 : 0128182229
Total Pages : 294 pages
Book Rating : 4.22/5 ( download)

DOWNLOAD NOW!

Download or read book Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation written by Liangzhi Cao and published by Woodhead Publishing. This book was released on 2020-08-30 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation presents the latest deterministic numerical methods for neutron transport equations (NTEs) with complex geometry, which are of great demand in recent years due to the rapid development of advanced nuclear reactor concepts and high-performance computational technologies. This book covers the wellknown methods proposed and used in recent years, not only theoretical modeling but also numerical results. This book provides readers with a very thorough understanding of unstructured neutron transport calculations and enables them to develop their own computational codes. The fundamentals, numerical discretization methods, algorithms, and numerical results are discussed. Researchers and engineers from utilities and research institutes are provided with examples on how to model an advanced nuclear reactor, which they can then apply to their own research projects and lab settings. Combines the theoretical models with numerical methods and results in one complete resource Presents the latest progress on the topic in an easy-to-navigate format

Author : Liangzhi Cao
Publisher : Woodhead Publishing
ISBN 13 : 0323858759
Total Pages : 412 pages
Book Rating : 4.55/5 ( download)

DOWNLOAD NOW!

Download or read book Resonance Self-Shielding Calculation Methods in Nuclear Reactors written by Liangzhi Cao and published by Woodhead Publishing. This book was released on 2022-10-01 with total page 412 pages. Available in PDF, EPUB and Kindle. Book excerpt: Resonance Self-Shielding Calculation Methods in Nuclear Reactors presents the latest progress in resonance self-shielding methods for both deterministic and Mote Carlo methods, including key advances over the last decade such as high-fidelity resonance treatment, resonance interference effect and multi-group equivalence. As the demand for high-fidelity resonance self-shielding treatment is increasing due to the rapid development of advanced nuclear reactor concepts and progression in high performance computational technologies, this practical book guides students and professionals in nuclear engineering and technology through various methods with proven high precision and efficiency. Presents a collection of resonance self-shielding methods, as well as numerical methods and numerical results Includes new topics in resonance self-shielding treatment Provides source codes of key calculations presented

Author : Guriĭ Ivanovich Marchuk
Publisher : Harwood Academic Publishers
ISBN 13 :
Total Pages : 632 pages
Book Rating : 4.11/5 ( download)

DOWNLOAD NOW!

Download or read book Numerical Methods in the Theory of Neutron Transport written by Guriĭ Ivanovich Marchuk and published by Harwood Academic Publishers. This book was released on 1986 with total page 632 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.48/5 ( download)

DOWNLOAD NOW!

Download or read book Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The research team has developed a practical, high-order, discrete-ordinates, short characteristics neutron transport code for three-dimensional configurations represented on unstructured tetrahedral grids that can be used for realistic reactor physics applications at both the assembly and core levels. This project will perform a comprehensive verification and validation of this new computational tool against both a continuous-energy Monte Carlo simulation (e.g. MCNP) and experimentally measured data, an essential prerequisite for its deployment in reactor core modeling. Verification is divided into three phases. The team will first conduct spatial mesh and expansion order refinement studies to monitor convergence of the numerical solution to reference solutions. This is quantified by convergence rates that are based on integral error norms computed from the cell-by-cell difference between the code's numerical solution and its reference counterpart. The latter is either analytic or very fine- mesh numerical solutions from independent computational tools. For the second phase, the team will create a suite of code-independent benchmark configurations to enable testing the theoretical order of accuracy of any particular discretization of the discrete ordinates approximation of the transport equation. For each tested case (i.e. mesh and spatial approximation order), researchers will execute the code and compare the resulting numerical solution to the exact solution on a per cell basis to determine the distribution of the numerical error. The final activity comprises a comparison to continuous-energy Monte Carlo solutions for zero-power critical configuration measurements at Idaho National Laboratory's Advanced Test Reactor (ATR). Results of this comparison will allow the investigators to distinguish between modeling errors and the above- listed discretization errors introduced by the deterministic method, and to separate the sources of uncertainty.

Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.10/5 ( download)

DOWNLOAD NOW!

Download or read book Numerical Formulation and Solution of Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Bengt G. Carlson
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.99/5 ( download)

DOWNLOAD NOW!

Download or read book Numerical Solution of Transient and Steady-state Neutron Transport Problems written by Bengt G. Carlson and published by . This book was released on 1959 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Elmer Eugene Lewis
Publisher : Wiley-Interscience
ISBN 13 :
Total Pages : 440 pages
Book Rating : 4.75/5 ( download)

DOWNLOAD NOW!

Download or read book Computational Methods of Neutron Transport written by Elmer Eugene Lewis and published by Wiley-Interscience. This book was released on 1984 with total page 440 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Author : Herbert Bishop Keller
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.90/5 ( download)

DOWNLOAD NOW!

Download or read book On the Numerical Integration of the Neutron Transport Equation written by Herbert Bishop Keller and published by . This book was released on 1955 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: A procedure for the direct numerical integration of the steady-state, elastic scattering neutron transport equation is presented.

Author : N. Khrennikov
Publisher :
ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.61/5 ( download)

DOWNLOAD NOW!

Download or read book Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data written by N. Khrennikov and published by . This book was released on 2006 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: The results of a study of neutron and gamma field functionals derived by deterministic Sn and Monte Carlo calculation methods and by neutron activation measurements in application to the ex-vessel cavity of the VVER-440 reactor Greifswald-1 are presented. A good agreement of deterministic and stochastic calculation results with each other as well as with measurement results was found for neutron threshold detector reaction rates at ex-vessel positions. The influence of different numbers of cross-sectional groups on the calculation results is demonstrated.

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.85/5 ( download)

DOWNLOAD NOW!

Download or read book Deterministic Methods for Time-dependent Stochastic Neutron Transport written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A numerical method is presented for solving the time-dependent survival probability equation in general (lD/2D/3D) geometries using the multi group SNmethod. Although this equation was first formulated by Bell in the early 1960's, it has only been applied to stationary systems (for other than idealized point models) until recently, and detailed descriptions of numerical solution techniques are lacking in the literature. This paper presents such a description and applies it to a dynamic system representative of a figurative criticality accident scenario.