Fission Gas Release from Thoria-based Fuels : Comparison with Model Predictions
Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
Published: 1980
Total Pages: 6
ISBN-13:
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Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
Published: 1980
Total Pages: 6
ISBN-13:
DOWNLOAD EBOOKAuthor: C. B. Cowking
Publisher:
Published: 1968
Total Pages: 0
ISBN-13:
DOWNLOAD EBOOKAuthor: John W. Prados
Publisher:
Published: 1961
Total Pages: 22
ISBN-13:
DOWNLOAD EBOOKAuthor: Nathan Christopher Andrews
Publisher:
Published: 2012
Total Pages: 149
ISBN-13:
DOWNLOAD EBOOKFuel swelling and fission gas generation for fast reactor fuels are of high importance since they are among the main limiting factors in the development of metallic fast reactor fuel. Five new fission gas and swelling modules for the fast reactor metallic fuel code FEAST-METAL were developed. This increases the number of degrees of freedom in the code and enhances the science -based modeling options for fuel swelling. All of the modules developed were benchmarked against data from EBRII. Particularly, the code was benchmarked against U-19Pu-lOZr fuel and was applied to U-6Zr fuel. The modifications made still kept the overall GRSIS algorithm present in the code. The GRSIS model tracks "closed" and "open" bubbles. The new modifications increased the number of closed bubble groups used in the algorithm, inserted a model that changed the bubble groups from being based on constant volumes to ones with constant numbers of atoms, added phase dependence and reexamined closed bubble spacing through the implementation of a Monte-Carlo algorithm to calculate the effective distance between the nearest bubbles. All model options added to the code predicted the swelling, fission gas release and cladding strain effectively for the benchmark cases. However, significant differences in the results were fotind when the codes were applied to long-term U-6Zr fuel. The differences in the results cannot be resolved without more data on fuel behavior under irradiation; particularly, breeder fuel (blanket) data is needed to develop effective benchmarks. Until more data becomes available, it is advisable to use the original two group constant volume version of the code and the phase dependent version of the code and compare the results. The latter offers a much more scientifically based version of the code. Sensitivity analysis to the number of bubble groups indicate limited benefit may be obtained by using more than 2 bubble sizes. Additionally, care should be taken to ensure that the axial nodding of the fuel be such that the axial mesh length is smaller than 10% of the fuel length. Furthermore, if the FEAST code is to be used in a coupled fashion with the coolant sub-channel analysis code COBRA, the accuracy of the results depend on the model used for fuel swelling.
Author: Yi Yuan
Publisher:
Published: 2000
Total Pages: 0
ISBN-13:
DOWNLOAD EBOOKAuthor: Dasarathi Das
Publisher: Springer Science & Business Media
Published: 2013-12-24
Total Pages: 423
ISBN-13: 1447155890
DOWNLOAD EBOOKThis book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuclear technology. In closing, the latest information on conventional uranium and plutonium fuels is also provided.
Author:
Publisher:
Published: 1965
Total Pages: 42
ISBN-13:
DOWNLOAD EBOOKAuthor: A.K. Nayak
Publisher: Springer
Published: 2019-01-30
Total Pages: 546
ISBN-13: 9811326584
DOWNLOAD EBOOKThis book comprises selected proceedings of the ThEC15 conference. The book presents research findings on various facets of thorium energy, including exploration and mining, thermo-physical and chemical properties of fuels, reactor physics, challenges in fuel fabrication, thorium fuel cycles, thermal hydraulics and safety, material challenges, irradiation experiences, and issues and challenges for the design of advanced thorium fueled reactors. Thorium is more abundant than uranium and has the potential to provide energy to the world for centuries if used in a closed fuel cycle. As such, technologies for using thorium for power generation in nuclear reactors are being developed worldwide. Since there is a strong global thrust towards designing nuclear reactors with thorium-based fuel, this book will be of particular interest to nuclear scientists, reactor designers, regulators, academics and policymakers.
Author: Robert P. Smith
Publisher:
Published: 1992
Total Pages: 196
ISBN-13:
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Publisher:
Published: 1974
Total Pages: 0
ISBN-13:
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