Контакты/Проезд  Доставка и Оплата Помощь/Возврат
История
  +7 707 857-29-98
  +7(7172) 65-23-70
  10:00-18:00 пн-пт
  shop@logobook.kz
   
    Поиск книг                        
Найти
  Зарубежные издательства Российские издательства  
Авторы | Каталог книг | Издательства | Новинки | Учебная литература | Акции | Бестселлеры | |
 

Deterministic Numerical Methods For Unstructured-Mesh Neutron Transport Calculation, Cao, Liangzhi


Варианты приобретения
Цена: 207730.00T
Кол-во:
Наличие: Поставка под заказ.  Есть в наличии на складе поставщика.
Склад Америка: 227 шт.  
При оформлении заказа до: 2025-07-28
Ориентировочная дата поставки: Август-начало Сентября
При условии наличия книги у поставщика.

Добавить в корзину
в Мои желания

Автор: Cao, Liangzhi   (Линцзы Цао)
Название:  Deterministic Numerical Methods For Unstructured-Mesh Neutron Transport Calculation
Перевод названия: Линцзы Цао: Детерминированные численные методы расчета переноса нейтронов в неструктурированной сетк
ISBN: 9780128182215
Издательство: Elsevier Science
Классификация:


ISBN-10: 0128182210
Обложка/Формат: Paperback
Вес: 4.79 кг.
Дата издания: 01.10.2020
Серия: Woodhead publishing series in energy
Язык: English
Размер: 228 x 151 x 20
Ссылка на Издательство: Link
Рейтинг:
Поставляется из: Европейский союз
Описание:

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.



Название: Deterministic Safety Analysis for Nuclear Power Plants
ISBN: 9204018143 ISBN-13(EAN): 9789204018141
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 21250.00 T
Наличие на складе: Невозможна поставка.
Описание: Provides harmonized guidance to designers, operators, regulators and providers of technical support on deterministic safety analysis for nuclear power plants. This guide provides information on the utilization of the results of such analysis for safety and reliability improvements.

Deterministic Safety Analysis for Nuclear Power Plants

Название: Deterministic Safety Analysis for Nuclear Power Plants
ISBN: 9201021194 ISBN-13(EAN): 9789201021199
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 38810.00 T
Наличие на складе: Нет в наличии.
Описание: This publication has been updated to maintain consistency with current IAEA safety requirements and to reflect lessons from the Fukushima Daiichi accident. It takes into account current practices and experience from deterministic safety analyses for NPPs being performed around the world

Название: Deterministic Safety Analysis for Nuclear Power Plants
ISBN: 9203330100 ISBN-13(EAN): 9789203330107
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 21250.00 T
Наличие на складе: Невозможна поставка.
Описание: Presents harmonized guidance to designers, operators, regulators and providers of technical support on deterministic safety analysis for nuclear power plants. This guide provides information on the utilization of the results of such analysis for safety and reliability improvements. It addresses conservative, best estimate and uncertainty evaluation approaches to deterministic safety analysis.

Fractional-order Modeling of Nuclear Reactor: From Subdiffusive Neutron Transport to Control-oriented Models

Автор: Vishwesh Vyawahare; Paluri S. V. Nataraj
Название: Fractional-order Modeling of Nuclear Reactor: From Subdiffusive Neutron Transport to Control-oriented Models
ISBN: 9811356556 ISBN-13(EAN): 9789811356551
Издательство: Springer
Рейтинг:
Цена: 107130.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This book addresses the topic of fractional-order modeling of nuclear reactors. Approaching neutron transport in the reactor core as anomalous diffusion, specifically subdiffusion, it starts with the development of fractional-order neutron telegraph equations. Using a systematic approach, the book then examines the development and analysis of various fractional-order models representing nuclear reactor dynamics, ultimately leading to the fractional-order linear and nonlinear control-oriented models. The book utilizes the mathematical tool of fractional calculus, the calculus of derivatives and integrals with arbitrary non-integer orders (real or complex), which has recently been found to provide a more compact and realistic representation to the dynamics of diverse physical systems.Including extensive simulation results and discussing important issues related to the fractional-order modeling of nuclear reactors, the book offers a valuable resource for students and researchers working in the areas of fractional-order modeling and control and nuclear reactor modeling.

Fractional-order Modeling of Nuclear Reactor: From Subdiffusive Neutron Transport to Control-oriented Models

Автор: Vyawahare
Название: Fractional-order Modeling of Nuclear Reactor: From Subdiffusive Neutron Transport to Control-oriented Models
ISBN: 9811075867 ISBN-13(EAN): 9789811075865
Издательство: Springer
Рейтинг:
Цена: 93160.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Chapter 1. Fractional Calculus.- Chapter 2. Introduction to Nuclear Reactor Modeling.- Chapter 3. Development and Analysis of Fractional-order Neutron Telegraph Equation.- Chapter 4. Development and Analysis of Fractional-order Point Reactor Kinetics Model.- Chapter 5. Further Developments using Fractional-order Point Reactor Kinetics Model.- Chapter 6. Development and Analysis of Fractional-order Point Reactor Kinetics Models with Reactivity Feedback.- Chapter 7. Development and Analysis of Fractional-order Two-Group Models.


Spatially Dependent Integral Neutron Transport Theory for Heterogeneous Media Using Homogeneous Green`s Functions

Автор: Church John
Название: Spatially Dependent Integral Neutron Transport Theory for Heterogeneous Media Using Homogeneous Green`s Functions
ISBN: 0530002167 ISBN-13(EAN): 9780530002163
Издательство: Неизвестно
Рейтинг:
Цена: 80930.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Dissertation Discovery Company and University of Florida are dedicated to making scholarly works more discoverable and accessible throughout the world. This dissertation, "Spatially Dependent Integral Neutron Transport Theory for Heterogeneous Media Using Homogeneous Green's Functions" by John Phillips Church, was obtained from University of Florida and is being sold with permission from the author. A digital copy of this work may also be found in the university's institutional repository, IR@UF. The content of this dissertation has not been altered in any way. We have altered the formatting in order to facilitate the ease of printing and reading of the dissertation.

Spatially Dependent Integral Neutron Transport Theory for Heterogeneous Media Using Homogeneous Green`s Functions

Автор: Church John
Название: Spatially Dependent Integral Neutron Transport Theory for Heterogeneous Media Using Homogeneous Green`s Functions
ISBN: 0530002175 ISBN-13(EAN): 9780530002170
Издательство: Неизвестно
Рейтинг:
Цена: 114030.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Dissertation Discovery Company and University of Florida are dedicated to making scholarly works more discoverable and accessible throughout the world. This dissertation, "Spatially Dependent Integral Neutron Transport Theory for Heterogeneous Media Using Homogeneous Green's Functions" by John Phillips Church, was obtained from University of Florida and is being sold with permission from the author. A digital copy of this work may also be found in the university's institutional repository, IR@UF. The content of this dissertation has not been altered in any way. We have altered the formatting in order to facilitate the ease of printing and reading of the dissertation.

Название: BN-600 MOX Core Benchmark Analysis: Results from Phases 4 and 6 of a Coordinated Research Project on Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects
ISBN: 9201392109 ISBN-13(EAN): 9789201392107
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: Presents the main results and achievements of an undertaking devoted to the benchmark analyses of two mixed oxide (MOX) fuelled BN-600 core designs. The studies conducted contributed to the progress in development, verification and validation of new codes and data libraries for fast reactor analyses.


Казахстан, 010000 г. Астана, проспект Туран 43/5, НП2 (офис 2)
ТОО "Логобук" Тел:+7 707 857-29-98 ,+7(7172) 65-23-70 www.logobook.kz
Kaspi QR
   В Контакте     В Контакте Мед  Мобильная версия