Author: K. M. WasywichPublisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Characteristics of Used CANDU Fuel Relevant to the Canadian Nuclear Fuel Waste Management Program
Author: K. M. WasywichPublisher: Pinawa, Man. : Whiteshell Laboratories
ISBN: 9780660151625
Category : Spent reactor fuels
Languages : en
Pages : 159
Book Description
Guide to Nuclear Power Cost Evaluation: Equipment costs
Author: Kaiser EngineersPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 140
Book Description
Pellet-clad Interaction in Water Reactor Fuels
Author: Publisher: OECD Publishing
ISBN:
Category : Business & Economics
Languages : en
Pages : 562
Book Description
This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.
Alternative Automotive Fuels
Author: United States. Congress. House. Committee on Energy and Commerce. Subcommittee on Energy and PowerPublisher:
ISBN:
Category : Alcohol as fuel
Languages : en
Pages : 510
Book Description
Reactor Core Materials
Author: Proceedings of the International Topical Meeting on LWR Fuel Performance
Author: Publisher:
ISBN: 9780894480324
Category : Light water reactors
Languages : en
Pages : 378
Book Description
Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
Author: International Atomic Energy AgencyPublisher: 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.
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.
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.