Nuclear Reactor Analysis

Nuclear Reactor Analysis PDF Author: James J. Duderstadt
Publisher: Wiley
ISBN: 9780471223634
Category : Technology & Engineering
Languages : en
Pages : 0

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Book Description
Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design.

Nuclear Reactor Analysis

Nuclear Reactor Analysis PDF Author: James J. Duderstadt
Publisher: Wiley
ISBN: 9780471223634
Category : Technology & Engineering
Languages : en
Pages : 0

Get Book Here

Book Description
Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design.

Nuclear Fuel Safety Criteria

Nuclear Fuel Safety Criteria PDF Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 74

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Book Description
Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.

Simulation Using the Monte Carlo Method

Simulation Using the Monte Carlo Method PDF Author: Rocco F. Iuorno
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72

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Book Description


Reactor Core Materials

Reactor Core Materials PDF Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 244

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Book Description


Nuclear Fuel Cycle Science and Engineering

Nuclear Fuel Cycle Science and Engineering PDF Author: Ian Crossland
Publisher: Elsevier
ISBN: 0857096389
Category : Business & Economics
Languages : en
Pages : 649

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Book Description
The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field.Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management.With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. - Provides a comprehensive and holistic review of the complete nuclear fuel cycle - Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis - Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication

Status of Fast Reactor Research and Technology Development

Status of Fast Reactor Research and Technology Development PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0

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Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.

Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants

Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants PDF Author: Robert Martin
Publisher: World Scientific
ISBN: 9813275677
Category : Technology & Engineering
Languages : en
Pages : 717

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Book Description
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)

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201080202
Category :
Languages : en
Pages : 218

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Book Description
This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.

The Linear Reactivity Model for Nuclear Fuel Management

The Linear Reactivity Model for Nuclear Fuel Management PDF Author: M. J. Driscoll
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 270

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Book Description
The Linear Reactivity Model (LRM) is a simple nuclear fuel management model that comes with a diskette containing three programs. Consisting of a collection of algorithms and methods, the LRM describes complex core behavior, but it is simpler than the complex programs developed for design calculations. This makes the LRM particularly useful as a teaching tool to explain the basic principles of nuclear fuel management. The LRM mainly focuses on the pressurized water reactor, but it is also directly applicable to the boiling water reactor. Application of the LRM to the CANDU reactor is also covered.

Pellet-clad Interaction in Water Reactor Fuels

Pellet-clad Interaction in Water Reactor Fuels PDF Author:
Publisher: OECD Publishing
ISBN:
Category : Business & Economics
Languages : en
Pages : 562

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Book Description
This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.