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Author : Lars Olof Jernkvist
Publisher :
ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.:/5 (319 download)
Download or read book A Model for Fission Gas Release from Mixed Oxide Nuclear Fuel written by Lars Olof Jernkvist and published by . This book was released on 2007 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher : Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development
ISBN 13 :
Total Pages : 572 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fission Gas Behaviour in Water Reactor Fuels written by and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt: Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Author : Ralph O. Meyer
Publisher :
ISBN 13 :
Total Pages : 68 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fission Gas Release from Fuel at High Burnup written by Ralph O. Meyer and published by . This book was released on 1978 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : H. Matzke
Publisher : Elsevier
ISBN 13 : 0444596836
Total Pages : 359 pages
Book Rating : 4.4/5 (445 download)
Download or read book Nuclear Materials for Fission Reactors written by H. Matzke and published by Elsevier. This book was released on 2012-12-02 with total page 359 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume brings together 47 papers from scientists involved in the fabrication of new nuclear fuels, in basic research of nuclear materials, their application and technology as well as in computer codes and modelling of fuel behaviour. The main emphasis is on progress in the development of non-oxide fuels besides reporting advances in the more conventional oxide fuels. The two currently performed large reactor safety programmes CORA and PHEBUS-FP are described in invited lectures. The contributions review basic property measurements, as well as the present state of fuel performance modelling. The performance of today's nuclear fuel, hence UO2, at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called "rim" effect. Similar phenomena can be simulated by ion implantation in order to better elucidate the underlying mechanism and reviews on high resolution electron microscopy provide further information. The papers will provide a useful treatise of views, ideas and new results for all those scientists and engineers involved in the specific questions of current nuclear waste management.
Author : John W. Prados
Publisher :
ISBN 13 :
Total Pages : 22 pages
Book Rating : 4.3/5 (91 download)
Download or read book A Model for Fission-gas Release from Porous Fuels in Low-permeability Containers written by John W. Prados and published by . This book was released on 1961 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Markus H.A. Piro
Publisher : Woodhead Publishing
ISBN 13 : 008102651X
Total Pages : 672 pages
Book Rating : 4.0/5 (81 download)
Download or read book Advances in Nuclear Fuel Chemistry written by Markus H.A. Piro and published by Woodhead Publishing. This book was released on 2020-03-20 with total page 672 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs
Author : Günther Kessler
Publisher : Springer Science & Business Media
ISBN 13 : 3709176220
Total Pages : 278 pages
Book Rating : 4.7/5 (91 download)
Download or read book Nuclear Fission Reactors written by Günther Kessler and published by Springer Science & Business Media. This book was released on 2013-03-07 with total page 278 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear power offers an abundant energy supply for the long term and at reasonable costs. Both are badly needed in this world of limited energy reserves and rising energy prices. On the other hand, there are questions widely discussed in the public on nuclear safety, on acceptable means of nuclear waste disposal, and concern on the proliferation of nuclear weapon capabilities. Public confu sion is widespread since facts are often overshadowed by emotions. Recognizing the need for reliable, factual and comprehensive information on nuclear energy, this book on Nuclear Fission Reactors is published .to present the scientific and technical facts of nuclear fission reactors, and to analyse their potential role and risks. The author, Professor Dr. G. Kessler, has worked in nuclear research and project management since 1963. From 1975 to 1978, he acted as project leader for the German/Belgian/Dutch Fast Breeder research and. development activi ties. Since then, he has been Director of the Institute of Neutron Physics and Reactor Technology in the Karlsruhe Nuclear Research Centre. The book is part of the series "Topics in Energy" issued by Springer Publish ers. The intention of this series of in-depth analyses is to present the facts, inherent problems, trends and prospects of energy demand, resources and tech nologies. The vital importance of energy for human activities has become apparent to the public particularly through dramatic events in the area of oil supply.
![Download Steady-state and Transient Fission Gas Release and Swelling Model for LIFE-4. [LMFBR]. PDF Online Free](https://books.google.com/books/content/images/frontcover/wrxRnQAACAAJ?fife=w200-h370)
Download or read book Steady-state and Transient Fission Gas Release and Swelling Model for LIFE-4. [LMFBR]. written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The fuel-pin modeling code LIFE-4 and the mechanistic fission gas behavior model FASTGRASS have been coupled and verified against gas release data from mixed-oxide fuels which were transient tested in the TREAT reactor. Design of the interface between LIFE-4 and FASTGRASS is based on an earlier coupling between an LWR version of LIFE and the GRASS-SST code. Fission gas behavior can significantly affect steady-state and transient fuel performance. FASTGRASS treats fission gas release and swelling in an internally consistent manner and simultaneously includes all major mechanisms thought to influence fission gas behavior. The FASTGRASS steady-state and transient analysis has evolved through comparisons of code predictions with fission-gas release and swelling data from both in- and ex-reactor experiments. FASTGRASS was chosen over other fission-gas behavior models because of its availability, its compatibility with the LIFE-4 calculational framework, and its predictive capability.
Author : Yanin Sukjai
Publisher :
ISBN 13 :
Total Pages : 464 pages
Book Rating : 4.:/5 (15 download)
Download or read book Fuel Performance Modeling of High Burnup Mixed Oxide Fuel for Hard Spectrum LWRs written by Yanin Sukjai and published by . This book was released on 2018 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt: According to the future of the nuclear fuel cycle study at MIT, a reactor with a conversion ratio around one can achieve desired objectives in the long-term sustainability of uranium and reduction of transuranic wastes. This finding relaxes the need for sodium fast reactors (SFR) in a closed-loop nuclear fuel cycle and enables high-conversion light water reactors (HC-LWR) to be used as an alternative. HC-LWRs have two major advantages over SFRs. First, apart from the reactor core, the remaining reactor system can be based on existing LWR technology. Second, extensive operating experience and a proven record of high reliability of LWRs would ease licensing and commercialization processes. Therefore, operating HC-LWRs instead of SFRs may be more economically and technically viable with lower capital and development cost for the near term. This type of reactor is being developed by Hitachi Ltd. under the name of resource-renewable boiling water reactor (RBWR). This study focuses on RBWR-TB2, transuranic burning version of RBWR. To demonstrate that the RBWR-TB2 can operate safely within design constraints and regulatory limits, the thermomechanical behavior of this reactor has been analyzed through fuel performance modeling. Due to its unique design characteristics, several physical phenomena at high temperature and high burnup typically ignored in most LWR fuel performance codes can potentially become active under RBWR’s operating conditions. These phenomena involve migration of fuel constituents and fission products, the evolution of O/M ratio with burnup, high burnup structure (HBS) formation, accelerated corrosion, hot pressing, gaseous fuel swelling, hydride precipitation and hydrogen migration in the cladding. Semi-empirical models describing porosity and cesium migration behaviors have been replaced with mechanistic models. All of these phenomena have been successfully implemented in a modified version of FRAPCON-3.5 known as FRAPCON-3.5 EP where EP stands for enhanced performance. The fuel performance comparison between RBWR-TB2 and ABWR fuel rods suggest that because of high axial peaking factors and relatively flat power history, fuel temperature is significantly higher in fissile zones of the RBWR-TB2 leading to various undesirable effects such as excessive fission gas release and cladding deformation. Local fuel burnup in fissile zones of RBWR-TB2 is multiple times higher than that of ABWR leading to excessive fuel swelling, accelerated cladding oxidation, and PCMI at fissile-blanket interfaces. Even if the RBWR-TB2 has to operate under such demanding conditions with a small margin to fuel melting, a steady-state fuel performance analysis still shows that this reactor can operate safely with an acceptable thermo-mechanical performance. In the future optimization of RBWR-TB2 performance, several fuel design strategies are recommended based on a series of sensitivity studies. The sensitivity study on key design parameters indicates that using annular fuel geometry and more hypostoichiometric fuel (lower O/M ratio) could reduce fuel temperature at high burnup. For better resistance to cladding corrosion and PCMI, it is recommended to increase cladding thickness and decrease fuel density.
Author : Masato Kato
Publisher : CRC Press
ISBN 13 : 1000686000
Total Pages : 183 pages
Book Rating : 4.0/5 (6 download)
Download or read book Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide written by Masato Kato and published by CRC Press. This book was released on 2022-10-17 with total page 183 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development. Features: Concisely covers the essential aspects of MOX nuclear fuels. Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model. Presents fuel property simulation technology. Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion. Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients. The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.
Author : C. Baker
Publisher :
ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (114 download)
Download or read book The Fission Gas Bubble Distribution in a Mixed Oxide Fast Reactor Fuel Pin written by C. Baker and published by . This book was released on 1977 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Pierre Zaleski
Publisher :
ISBN 13 :
Total Pages : 602 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Energy Maturity: Nuclear fuel performance and management, pt. 1 written by Pierre Zaleski and published by . This book was released on 1976 with total page 602 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fission Gas Behavior in Mixed-Oxide Fuel During Transient Overpower written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Peter von der Hardt
Publisher : Harwood Academic Publishers
ISBN 13 : 9783718600168
Total Pages : 664 pages
Book Rating : 4.6/5 (1 download)
Download or read book Aspects of Nuclear Reactor Safety written by Peter von der Hardt and published by Harwood Academic Publishers. This book was released on 1980 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Atomic Energy of Canada Limited
Publisher : Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN 13 :
Total Pages : 11 pages
Book Rating : 4.:/5 (159 download)
Download or read book Prediction of Fission Gas Release from High Burnup Oxide Fuel written by Atomic Energy of Canada Limited and published by Chalk River, Ont. : Chalk River Nuclear Laboratories. This book was released on 1979 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (14 download)
Download or read book Prediction of Fission Gas Release from High Burnup Oxide Fuel written by and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Benjamin Lustman
Publisher :
ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.3/5 (91 download)
Download or read book Release of Fission Gases from U02 written by Benjamin Lustman and published by . This book was released on 1957 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
