Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5

Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201043191
Category : Business & Economics
Languages : en
Pages : 65

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Book Description
This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.

Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5

Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5 PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201043191
Category : Business & Economics
Languages : en
Pages : 65

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Book Description
This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.

Operating Summary

Operating Summary PDF Author: United States. General Services Administration
Publisher:
ISBN:
Category : Government property
Languages : en
Pages : 36

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Book Description


Nuclear Regulatory Commission Issuances

Nuclear Regulatory Commission Issuances PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950

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Book Description


Internationalization of the Nuclear Fuel Cycle

Internationalization of the Nuclear Fuel Cycle PDF Author: Russian Academy of Sciences
Publisher: National Academies Press
ISBN: 0309185947
Category : Science
Languages : en
Pages : 172

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Book Description
The so-called nuclear renaissance has increased worldwide interest in nuclear power. This potential growth also has increased, in some quarters, concern that nonproliferation considerations are not being given sufficient attention. In particular, since introduction of many new power reactors will lead to requiring increased uranium enrichment services to provide the reactor fuel, the proliferation risk of adding enrichment facilities in countries that do not have them now led to proposals to provide the needed fuel without requiring indigenous enrichment facilities. Similar concerns exist for reprocessing facilities. Internationalization of the Nuclear Fuel Cycle summarizes key issues and analyses of the topic, offers some criteria for evaluating options, and makes findings and recommendations to help the United States, the Russian Federation, and the international community reduce proliferation and other risks, as nuclear power is used more widely. This book is intended for all those who are concerned about the need for assuring fuel for new reactors and at the same time limiting the spread of nuclear weapons. This audience includes the United States and Russia, other nations that currently supply nuclear material and technology, many other countries contemplating starting or growing nuclear power programs, and the international organizations that support the safe, secure functioning of the international nuclear fuel cycle, most prominently the International Atomic Energy Agency.

Nuclear Energy Basic Principles

Nuclear Energy Basic Principles PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201126085
Category : Business & Economics
Languages : en
Pages : 0

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Book Description
Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.

Nuclear Fuel Cycle Simulation System (VISTA)

Nuclear Fuel Cycle Simulation System (VISTA) PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 112

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Book Description
The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.

The Future of Nuclear Fuel Cycle

The Future of Nuclear Fuel Cycle PDF Author:
Publisher:
ISBN: 9780982800843
Category : Energy policy
Languages : en
Pages : 237

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Book Description
"In this analysis we have presented a method that provides insight into future fuel cycle alternatives by clarifying the complexity of choosing an appropriate fuel cycle in the context of the distribution of burdens and benefits between generations. The current nuclear power deployment practices, together with three future fuel cycles were assessed."--Page 227.

Three Mile Island

Three Mile Island PDF Author: U.S. Nuclear Regulatory Commission. Special Inquiry Group
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 214

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Book Description


Post-irradiation Examination and In-pile Measurement Techniques for Water Reactor Fuels

Post-irradiation Examination and In-pile Measurement Techniques for Water Reactor Fuels PDF Author: International Atomic Energy Agency
Publisher: International Atomic Energy Agency
ISBN: 9789201627094
Category : Technology & Engineering
Languages : en
Pages :

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Book Description
This publication represents a summary and proceedings of two technical meetings on the subjects of 1) hot cell post-irradiation examination (PIE) techniques and poolside inspection of water reactor fuel assemblies, and 2) fuel rod instrumentation and in-pile measurement techniques. It provides an overview of the status of in-pile and post-irradiation techniques of water reactor fuel examination with an emphasis on experimental methods applied to high burnup fuel. Further important items addressed at these meetings were the information on progress achieved in non-destructive and destructive PIE techniques used for investigation of water reactor fuels, advanced PIE techniques such as 3-D tomography, as well as advanced in-pile measurement techniques for a better understanding of mechanisms of fuel behavior under irradiation.