Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
International Working Group on Water Reactor Fuel Performance and Technology : proceedings of a Technical Committee Meeting to Review the Status and Trends in the Area of Water Reactor Fuel Performance and Technology (15th Plenary Meeting of the IWGFPT), Vienna, Austria, 27-29 April 1999 : summary report
Author: Review of Fuel Failures in Water Cooled Reactors (2006-2015): IAEA Nuclear Energy Series No. Nf-T-2.5
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201043191
Category : Business & Economics
Languages : en
Pages : 65
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.
Water Reactor Fuel Element Performance Computer Modelling
Author: John GittusPublisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 736
Book Description
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Author: International Atomic Energy AgencyPublisher:
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.
Scientific Issues in Fuel Behaviour
Author: NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel BehaviourPublisher: OECD
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 96
Book Description
Dated January 1995
Nuclear Fuel Cycle Simulation System (VISTA)
Author: International Atomic Energy AgencyPublisher: 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.
Reactor Core Materials
Author: Nuclear Fuel Safety Criteria
Author: OECD Nuclear Energy AgencyPublisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 74
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.
Fuel Modelling in Accident Conditions
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201639196
Category : Technology & Engineering
Languages : en
Pages : 180
Book Description
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.
Nuclear Energy Basic Principles
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201126085
Category : Business & Economics
Languages : en
Pages : 0
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.