Deterministic Numerical Methods for Unstructured Mesh Neutron Transport Calculation

This book PDF is perfect for those who love Technology & Engineering genre, written by Liangzhi Cao and published by Woodhead Publishing which was released on 30 August 2020 with total hardcover pages 294. You could read this book directly on your devices with pdf, epub and kindle format, check detail and related Deterministic Numerical Methods for Unstructured Mesh Neutron Transport Calculation books below.

Deterministic Numerical Methods for Unstructured Mesh Neutron Transport Calculation
Author : Liangzhi Cao
File Size : 50,8 Mb
Publisher : Woodhead Publishing
Language : English
Release Date : 30 August 2020
ISBN : 9780128182222
Pages : 294 pages
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Deterministic Numerical Methods for Unstructured Mesh Neutron Transport Calculation by Liangzhi Cao Book PDF Summary

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

Deterministic Numerical Methods for Unstructured Mesh Neutron Transport Calculation

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