Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100
Book Description
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100
Book Description
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100
Book Description
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Guide to Nuclear Power Cost Evaluation: Equipment costs
Author: Kaiser Engineers
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 140
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 140
Book Description
Alternative Automotive Fuels
Author: United States. Congress. House. Committee on Energy and Commerce. Subcommittee on Energy and Power
Publisher:
ISBN:
Category : Alcohol as fuel
Languages : en
Pages : 510
Book Description
Publisher:
ISBN:
Category : Alcohol as fuel
Languages : en
Pages : 510
Book Description
Proceedings of the International Topical Meeting on LWR Fuel Performance
Author:
Publisher:
ISBN: 9780894480324
Category : Light water reactors
Languages : en
Pages : 378
Book Description
Publisher:
ISBN: 9780894480324
Category : Light water reactors
Languages : en
Pages : 378
Book Description
Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program
Author: K. M. Wasywich
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Publisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
The Energy Dilemma
Author: Jared Keen
Publisher:
ISBN: 9781583401699
Category : Business & Economics
Languages : en
Pages : 54
Book Description
Explores the energy crisis on a global scale, covering the environmental, social, political, and economic implications of dependence on non-renewable energy sources.
Publisher:
ISBN: 9781583401699
Category : Business & Economics
Languages : en
Pages : 54
Book Description
Explores the energy crisis on a global scale, covering the environmental, social, political, and economic implications of dependence on non-renewable energy sources.
Nuclear Fuel Cycle Simulation System (VISTA)
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 112
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.
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 112
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.
Nuclear Engineering Handbook
Author: Kenneth D. Kok
Publisher: CRC Press
ISBN: 1315356309
Category : Science
Languages : en
Pages : 1328
Book Description
Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.
Publisher: CRC Press
ISBN: 1315356309
Category : Science
Languages : en
Pages : 1328
Book Description
Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.
Minor Actinide Burning in Thermal Reactors
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201080202
Category :
Languages : en
Pages : 218
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.
Publisher:
ISBN: 9789201080202
Category :
Languages : en
Pages : 218
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.