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Nuclear Power Plant Design And Analysis Codes, Wang, Jun


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Цена: 207730.00T
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Автор: Wang, Jun
Название:  Nuclear Power Plant Design And Analysis Codes
Перевод названия: Ван Цзюнь: Программы проектирования и анализа работы атомных установок
ISBN: 9780128181904
Издательство: Elsevier Science
Классификация:


ISBN-10: 0128181907
Обложка/Формат: Paperback
Вес: 1.03 кг.
Дата издания: 01.11.2020
Серия: Woodhead publishing series in energy
Язык: English
Размер: 229 x 152 x 32
Подзаголовок: Development, validation, and application
Ссылка на Издательство: Link
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Поставляется из: Европейский союз
Описание:

Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li, Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.

Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs.


Toward Consistent Design Evaluation of Nuclear Power Piping by Nonlinear Finite Element Analysis

Автор: Lingfu Zeng, Lennart Jansson, Nils-Erik Wiberg
Название: Toward Consistent Design Evaluation of Nuclear Power Piping by Nonlinear Finite Element Analysis
ISBN: 079186104X ISBN-13(EAN): 9780791861042
Издательство: Mare Nostrum (Eurospan)
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Цена: 110880.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Addresses a few issues essential for achieving a consistent Design-By-Analysis in accordance with the ASME Boiler & Pressure Vessel Code: nonlinear alternative rules, fatigue, thermal ratcheting, dynamic loads, strain-based criteria, nonlinear finite element procedures, supports under combined stresses, and others.

Nuclear Power Plant Safety and Mechanical Integrity

Автор: George Antaki
Название: Nuclear Power Plant Safety and Mechanical Integrity
ISBN: 0124172482 ISBN-13(EAN): 9780124172487
Издательство: Elsevier Science
Рейтинг:
Цена: 123520.00 T
Наличие на складе: Поставка под заказ.
Описание: One of the most critical requirements for safe and reliable nuclear power plant operations is the availability of competent maintenance personnel. However, just as the nuclear power industry is experiencing a renaissance, it is also experiencing an exodus of seasoned maintenance professionals due to retirement. The perfect guide for engineers just entering the field or experienced maintenance supervisors who need to keep abreast of the latest industry best practices, Nuclear Power Plant Maintenance: Mechanical Systems, Equipment and Safety covers the most common issues faced in day-to-day operations and provides practical, technically proven solutions. The book also explains how to navigate the various maintenance codes, standards and regulations for the nuclear power industry.

Design-Basis Accident Analysis Methods for Light-Water Nuclear Power Plants

Автор: Martin Robert, Frepoli Cesare
Название: Design-Basis Accident Analysis Methods for Light-Water Nuclear Power Plants
ISBN: 9813275650 ISBN-13(EAN): 9789813275652
Издательство: World Scientific Publishing
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Цена: 248160.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

Название: Evaluation of Advanced Thermohydraulic System Codes for Design and Safety Analysis of Integral Type Reactors
ISBN: 9201003145 ISBN-13(EAN): 9789201003140
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: Presents the outcome of an International Collaborative Standard Problems assessing the capability of system thermohydraulic computer codes for integral reactor system design and safety analysis. The publication details the ICSP tests and results from all participants.

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.

Benchmarking of computational fluid dynamics codes for fuel assembly design

Автор: Iaea
Название: Benchmarking of computational fluid dynamics codes for fuel assembly design
ISBN: 9201068204 ISBN-13(EAN): 9789201068200
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: Draws on the work carried out during an IAEA coordinated research project to benchmark computational fluid dynamics (CFD) codes used in fuel assembly design and model options and methods against `CFD quality` experimental data under single phase flow conditions.

Benchmarking of computational fluid dynamics codes for reactor vessel design

Автор: Iaea
Название: Benchmarking of computational fluid dynamics codes for reactor vessel design
ISBN: 9201074204 ISBN-13(EAN): 9789201074201
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: This publication provides a description of the Rossendorf coolant mixing (ROCOM) test facility, used to provide benchmark experiments related to the phenomena of pressurized thermal shock (PTS) and boron dilution, the calculation results using computational fluid dynamics (CFD) codes and methods, and the conclusions drawn from comparison of CFD results with experimental measurements. The aim of this benchmarking was to provide CFD practitioners with two high quality datasets of relevance to reactor transients inside a pressurized water reactor pressure vessel with different configurations and involving mixed convection, stratification, jet impingement and unsteady (inverse) plumes. The focus of the benchmarking was on the three main regions of the cold domain of the primary circuit, i.e. the cold leg, the downcomer and the core entry region. The work was carried out within the framework of an IAEA coordinated research project on application of computational fluid dynamics codes to nuclear power plant design.

Application of Plant Information Models to Manage Design Knowledge through the Nuclear Power Plant Life Cycle

Название: Application of Plant Information Models to Manage Design Knowledge through the Nuclear Power Plant Life Cycle
ISBN: 9201111207 ISBN-13(EAN): 9789201111203
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Нет в наличии.
Описание: A plant information model (PIM) is a set of interlinked information about plant structures, systems and components, incorporating plant data, relationships and rules used to integrate, represent, and describe nuclear facility processes and data, for each phase of the facility lifecycle. Application of the PIM provides an opportunity to radically improve knowledge, information and data capture, integration, use and transfer between stakeholders if industry-wide standards and best practices are adopted. A knowledge-centric plant information model could be developed and leveraged as a modern and efficient approach to better support, manage and enable seamless sharing, transfer and use of sustainable design knowledge within and across each nuclear power plant life cycle phase. The purpose of this publication is to provide an overview of PIMs, emphasize the importance of their application in support and management of design knowledge throughout the nuclear power plant life cycle and present an overview of a knowledge-centric plant information model that builds on the basic concept of a PIM. The target users of this publication are decision-making organizations in Member States having experience with nuclear power programmes and those embarking on new nuclear power programmes.

Foundations in Applied Nuclear Engineering Analysis (2nd Edition)

Автор: Sjoden Glenn E.
Название: Foundations in Applied Nuclear Engineering Analysis (2nd Edition)
ISBN: 9814630934 ISBN-13(EAN): 9789814630931
Издательство: World Scientific Publishing
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Цена: 68640.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Foundations In Applied Nuclear Engineering Analysis (2Nd Edition) Covers A Fast-Paced One Semester Course To Address Concepts Of Modeling In Mathematics, Engineering Analysis, And Computational Problem Solving Needed In Subjects Such As Radiation Interactions, Heat Transfer, Reactor Physics, Radiation Transport, Numerical Modeling, Etc., For Success In A Nuclear Engineering/Medical Physics Curriculum. While Certain Topics Are Covered Tangentially, Others Are Covered In Depth To Target On The Appropriate Amalgam Of Topics For Success In Navigating Nuclear-Related Disciplines. Software Examples And Programming Are Used Throughout The Book, Since Computational Capabilities Are Essential For New Engineers.The Book Contains A Array Of Topics That Cover The Essential Subjects Expected For Students To Successfully Navigate Into Nuclear-Related Disciplines. The Text Assumes That Students Have Familiarity With Undergraduate Mathematics And Physics, And Are Ready To Apply Those Skills To Problems In Nuclear Engineering. Applications And Problem Sets Are Directed Toward Problems In Nuclear Science. Software Examples Using Mathematica Software Are Used In The Text.This Text Was Developed As Part Of A Very Applied Course In Mathematical Physics Methods For Nuclear Engineers. The Course In Nuclear Engineering Analysis That Follows This Text Began At The University Of Florida; The 2Nd Edition Was Released While At The Georgia Institute Of Technology.

Foundations in Applied Nuclear Engineering Analysis (2nd Edition)

Автор: Sjoden Glenn E.
Название: Foundations in Applied Nuclear Engineering Analysis (2nd Edition)
ISBN: 9814630926 ISBN-13(EAN): 9789814630924
Издательство: World Scientific Publishing
Рейтинг:
Цена: 111930.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Foundations In Applied Nuclear Engineering Analysis (2Nd Edition) Covers A Fast-Paced One Semester Course To Address Concepts Of Modeling In Mathematics, Engineering Analysis, And Computational Problem Solving Needed In Subjects Such As Radiation Interactions, Heat Transfer, Reactor Physics, Radiation Transport, Numerical Modeling, Etc., For Success In A Nuclear Engineering/Medical Physics Curriculum. While Certain Topics Are Covered Tangentially, Others Are Covered In Depth To Target On The Appropriate Amalgam Of Topics For Success In Navigating Nuclear-Related Disciplines. Software Examples And Programming Are Used Throughout The Book, Since Computational Capabilities Are Essential For New Engineers.The Book Contains A Array Of Topics That Cover The Essential Subjects Expected For Students To Successfully Navigate Into Nuclear-Related Disciplines. The Text Assumes That Students Have Familiarity With Undergraduate Mathematics And Physics, And Are Ready To Apply Those Skills To Problems In Nuclear Engineering. Applications And Problem Sets Are Directed Toward Problems In Nuclear Science. Software Examples Using Mathematica Software Are Used In The Text.This Text Was Developed As Part Of A Very Applied Course In Mathematical Physics Methods For Nuclear Engineers. The Course In Nuclear Engineering Analysis That Follows This Text Began At The University Of Florida; The 2Nd Edition Was Released While At The Georgia Institute Of Technology.

Nuclear Power in India: A Comparative Analysis

Автор: David Hart
Название: Nuclear Power in India: A Comparative Analysis
ISBN: 0367230968 ISBN-13(EAN): 9780367230968
Издательство: Taylor&Francis
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Цена: 91860.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Originally published in 1983. This extremely informative account will appeal to readers with interest in energy, science, technology and Third World developments, and in nuclear proliferation in the Third World.

Название: Data Analysis and Collection for Costing of Research Reactor Decommissioning
ISBN: 9201087179 ISBN-13(EAN): 9789201087171
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: This publication is intended to assist those Member States with limited decommissioning expertise, to estimate the overall cost of decommissioning during the early planning stages. The lack of published data has made it difficult to benchmark estimated costs against international practice. The DACCORD (data analysis and collection for costing of research reactor decommissioning) project was established to address this deficiency. Based on the outcome of the three main working groups, this publication provides representative input data and benchmarking data needed for the costing of research reactor decommissioning at preliminary planning stages. All detailed cost cases considered in the DACCORD project are presented in a special format, following a software tool, developed by the IAEA, and which helps to ensure uniformity of the presented data and generally to facilitate the analysis of the available information.


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