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Nuclear Materials Science
  • Language: en

Nuclear Materials Science

  • Type: Book
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  • Published: 2016
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  • Publisher: Unknown

Annotation 'Nuclear Materials Science' takes students from understanding standard materials science and engineering and uses it as a base to work from in teaching the additional requirements of nuclear engineering science.

Comprehensive Nuclear Materials
  • Language: en
  • Pages: 3552

Comprehensive Nuclear Materials

  • Type: Book
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  • Published: 2011-05-12
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  • Publisher: Elsevier

Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants

Accident-Tolerant Materials for Light Water Reactor Fuels
  • Language: en
  • Pages: 236

Accident-Tolerant Materials for Light Water Reactor Fuels

  • Type: Book
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  • Published: 2020-01-16
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  • Publisher: Elsevier

Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic.

Nuclear Fuel Safety Criteria
  • Language: en
  • Pages: 74

Nuclear Fuel Safety Criteria

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.

Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design
  • Language: en
  • Pages: 74

Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design

  • Type: Book
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  • Published: 1962
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  • Publisher: Unknown

None

Three Mile Island, Chernobyl and Fukushima
  • Language: en
  • Pages: 126

Three Mile Island, Chernobyl and Fukushima

  • Type: Book
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  • Published: 2016-11-08
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  • Publisher: Springer

This book examines the three most well-known and socially important nuclear accidents. Each of these accidents had significant, yet dramatically different, human and environmental impacts. Unique factors helped shape the overall pattern and scale of each disaster, but a major contributing factor was the different designs used for each reactor. Fukushima was a boiling water reactor (BWR), Chernobyl was a graphite moderated boiling water reactor, and TMI was a pressurized water reactor (PWR). This book traces the history of nuclear power and the development of each reactor type. We examine how GE’s work with a sodium cooled design did not fare well with the US Navy, and led GE to promulgate ...

Nuclear Fuel Elements
  • Language: en
  • Pages: 284

Nuclear Fuel Elements

  • Type: Book
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  • Published: 2013-10-22
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  • Publisher: Elsevier

Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the...

Thermal and Reliability Criteria for Nuclear Fuel Safety
  • Language: en

Thermal and Reliability Criteria for Nuclear Fuel Safety

  • Type: Book
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  • Published: 2024-10-21
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  • Publisher: Unknown

The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience. The book starts by looking at the physical safety basis of water-water energetic reactor (WWER) nuclear fuel. It goes on to discuss modern approaches to the heat exchange modelling in nuclear power plant equipment. Next, the safety criteria when making a decision about dry storage for WWER-1000 fuel assembly are discussed. Then the effect of reactor capacity cyclic changes on energy accumulation of creep formations in fuel cladding is covered in full, along with a chapter on the analysis of WWER-1000 fuel cladding failure. Finally, the book finishes with a description of thermal safety criteria for dry storage of spent nuclear fuel. The book is essential reading for anyone concerned with NPP maintenance and safety.

The Change of Paradigm in Nuclear Fuel Optimization
  • Language: en
  • Pages: 210

The Change of Paradigm in Nuclear Fuel Optimization

This monograph highlights pertinent problems in nuclear fuel optimization. It shows that the current approach does not allow us to predict the synergic effects leading to fuel-related accidents, and is characterized by great uncertainty with regards to estimating fuel cladding failure conditions and the reduced efficiency of fuel operation. The book describes in detail a new philosophy of nuclear fuel optimization based on the synergic paradigm, applicable to both operating and prospective reactors, in order to minimize radioactive leakage under normal and emergency fuel operating conditions, to resolve the safety-efficiency contradiction for nuclear fuel operation, and to predict new synergic effects due to processes of self-organization in the reactor core. It will appeal to researchers, academics, PhD students and engineers engaged in developing prospective nuclear reactor designs, as well as those who verify the safety and efficiency of nuclear fuel operation under increasingly challenging core conditions.

Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water
  • Language: en
  • Pages: 236

Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water

  • Type: Book
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  • Published: 2003
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  • Publisher: Unknown

This report describes research performed in ten laboratories within the framework of the IAEA Co-ordinated Research Project on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water. The project consisted of exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water. A group of experts in the field contributed a state of the art review and provided technical supervision of the project. Localized corrosion mechanisms are notoriously difficult to understand, and it was clear from the outset that obtaining consistency in the results and their interpretation from laboratory to laboratory would depend on the development of an excellent set of experimental protocols. These experimental protocols are described in the report, together with guidelines for the maintenance of optimum water chemistry to minimize the corrosion of aluminium clad research reactor fuel in wet storage.