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

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

Author: International Atomic Energy Agency

Publisher:

Published: 2020-07-30

Total Pages: 218

ISBN-13: 9789201080202

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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.


Nuclear Fuel Cycle Simulation System (VISTA)

Nuclear Fuel Cycle Simulation System (VISTA)

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2007

Total Pages: 112

ISBN-13:

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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 Fuel Safety Criteria

Nuclear Fuel Safety Criteria

Author: OECD Nuclear Energy Agency

Publisher: OECD Publishing

Published: 2001

Total Pages: 74

ISBN-13:

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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.


Nuclear Energy Basic Principles

Nuclear Energy Basic Principles

Author: International Atomic Energy Agency

Publisher:

Published: 2008

Total Pages: 0

ISBN-13: 9789201126085

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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.


Fuel Modelling in Accident Conditions

Fuel Modelling in Accident Conditions

Author: International Atomic Energy Agency

Publisher:

Published: 2020-02-29

Total Pages: 180

ISBN-13: 9789201639196

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This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.


Fast Reactor Database 2006 Update

Fast Reactor Database 2006 Update

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2006

Total Pages: 462

ISBN-13:

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Liquid metal cooled fast reactors (LMFRs) have been under development for about 50 years. The fast reactor database (FRDB) summarised in this report contains detailed design and operational data on 37 fast reactor plants, their thermal power ranging from 10 to 4000 MW, covering experimental, prototype, demonstration and commercial size LMFRs. Data includes physical, hydraulic and thermomechanical characteristics, technological requirements and methods and criteria to ensure safe operation, as well as dimensions, materials information and main design features and performance parameters of reactor cores, components and various systems, along with sketches and drawings.