Fission-gas-bubble Mobility in Oxide Fuel

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Fission-gas-bubble Mobility in Oxide Fuel by :

Download or read book Fission-gas-bubble Mobility in Oxide Fuel written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The available volatile fission product release data has confirmed the general viability of the scaling model of volatile fission product release in which the fractional release rates of the volatile fission products scale as that of the fission gas. The question of whether fission gas bubbles can move sufficiently fast to be a significant mechanism responsible for fission gas release from the fuel is considered. The mean jump distance per jump of the hopping process in gas bubble motion is analyzed. Surface roughness is also considered.

Sensitivity of fission gas release from fuel to gas bubble mobility

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (59 download)

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Book Synopsis Sensitivity of fission gas release from fuel to gas bubble mobility by : I. R. Brearley

Download or read book Sensitivity of fission gas release from fuel to gas bubble mobility written by I. R. Brearley and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Aspects of Nuclear Reactor Safety

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Publisher : Harwood Academic Publishers
ISBN 13 : 9783718600168
Total Pages : 664 pages
Book Rating : 4.6/5 (1 download)

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Book Synopsis Aspects of Nuclear Reactor Safety by : Peter von der Hardt

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:

Sensitivity of Fission F^gas Release from Fuel to Gas Bubble Mobility

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ISBN 13 :
Total Pages : 8 pages
Book Rating : 4.:/5 (896 download)

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Book Synopsis Sensitivity of Fission F^gas Release from Fuel to Gas Bubble Mobility by : I.R. Brearley

Download or read book Sensitivity of Fission F^gas Release from Fuel to Gas Bubble Mobility written by I.R. Brearley and published by . This book was released on 1980 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fission-product Behavior in Ceramic Oxide Fuel

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Publisher :
ISBN 13 :
Total Pages : 320 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Fission-product Behavior in Ceramic Oxide Fuel by : Ian J. Hastings

Download or read book Fission-product Behavior in Ceramic Oxide Fuel written by Ian J. Hastings and published by . This book was released on 1986 with total page 320 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Fission Gas Bubble Distribution in a Mixed Oxide Fast Reactor Fuel Pin

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ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (114 download)

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Book Synopsis The Fission Gas Bubble Distribution in a Mixed Oxide Fast Reactor Fuel Pin by : C. Baker

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:

Characterization of Intergranular Fission Gas Bubbles in U-Mo Fuel

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (893 download)

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Book Synopsis Characterization of Intergranular Fission Gas Bubbles in U-Mo Fuel by :

Download or read book Characterization of Intergranular Fission Gas Bubbles in U-Mo Fuel written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report can be divided into two parts: the first part, which is composed of sections 1, 2, and 3, is devoted to report the analyses of fission gas bubbles; the second part, which is in section 4, is allocated to describe the mechanistic model development. Swelling data of irradiated U-Mo alloy typically show that the kinetics of fission gas bubbles is composed of two different rates: lower initially and higher later. The transition corresponds to a burnup of ≈0 at% U-235 (LEU) or a fission density of ≈3 x 1021 fissions/cm3. Scanning electron microscopy (SEM) shows that gas bubbles appear only on the grain boundaries in the pretransition regime. At intermediate burnup where the transition begins, gas bubbles are observed to spread into the intragranular regions. At high burnup, they are uniformly distributed throughout fuel. In highly irradiated U-Mo alloy fuel large-scale gas bubbles form on some fuel particle peripheries. In some cases, these bubbles appear to be interconnected and occupy the interface region between fuel and the aluminum matrix for dispersion fuel, and fuel and cladding for monolithic fuel, respectively. This is a potential performance limit for U-Mo alloy fuel. Microscopic characterization of the evolution of fission gas bubbles is necessary to understand the underlying phenomena of the macroscopic behavior of fission gas swelling that can lead to a counter measure to potential performance limit. The microscopic characterization data, particularly in the pre-transition regime, can also be used in developing a mechanistic model that predicts fission gas bubble behavior as a function of burnup and helps identify critical physical properties for the future tests. Analyses of grain and grain boundary morphology were performed. Optical micrographs and scanning electron micrographs of irradiated fuel from RERTR-1, 2, 3 and 5 tests were used. Micrographic comparisons between as-fabricated and as-irradiated fuel revealed that the site of first bubble appearance is the grain boundary. Analysis using a simple diffusion model showed that, although the difference in the Mo-content between the grain boundary and grain interior region decreased with burnup, a complete convergence in the Mo-content was not reached at the end of the test for all RERTR tests. A total of 13 plates from RERTR-1, 2, 3 and 5 tests with different as-fabrication conditions and irradiation conditions were included for gas bubble analyses. Among them, two plates contained powders [gamma]-annealed at ≈800 C for ≈100 hours. Most of the plates were fabricated with as-atomized powders except for two as-machined powder plates. The Mo contents were 6, 7 and 10wt%. The irradiation temperature was in the range 70-190 C and the fission rate was in the range 2.4 x 1014 - 7 x 1014 f/cm3-s. Bubble size for both of the [gamma]-annealed powder plates is smaller than the as-atomized powder plates. The bubble size for the as-atomized powder plates increases as a function of burnup and the bubble growth rate shows signs of slowing at burnups higher than ≈40 at% U-235 (LEU). The bubble-size distribution for all plates is a quasi-normal, with the average bubble size ranging 0.14-0.18 [mu]m. Although there are considerable errors, after an initial incubation period the average bubble size increases with fission density and shows saturation at high fission density. Bubble population (density) per unit grain boundary length was measured. The [gamma]-annealed powder plates have a higher bubble density per unit grain boundary length than the as-atomized powder plates. The measured bubble number densities per unit grain boundary length for as-atomized powder plates are approximately constant with respect to burnup. Bubble density per unit cross section area was calculated using the density per unit grain boundary length data. The grains were modeled as tetrakaidecahedrons. Direct measurements for some plates were also performed and compared with the calculated quantities. Bubble density per unit grain boundary surface area was calculated by using the density per unit grain boundary length data. These data were used as input for mechanistic modeling described in section 4. Volumetric bubble density was calculated by using density per unit grain boundary surface area. Based on these data, bubble volumetric fraction was calculated. Bubble volume fraction was also calculated by using the density per unit cross section area. Bubble volume fraction was also directly measured for some plates. These three results are comparable although the direct measurement data are slightly larger than the others. Bubble volume fraction increased as a function of burnup, reaching ≈2% of fuel volume at 3 x 1021 f/cm3. Fission gas bubble swelling is minor compared to that of solid fission product swelling.

A theoretical investigation of electron microscope observations of fission gas bubble distributions in a mixed oxide fast reactor fuel pin

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ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (865 download)

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Book Synopsis A theoretical investigation of electron microscope observations of fission gas bubble distributions in a mixed oxide fast reactor fuel pin by : M. H. Wood

Download or read book A theoretical investigation of electron microscope observations of fission gas bubble distributions in a mixed oxide fast reactor fuel pin written by M. H. Wood and published by . This book was released on 1977 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fission Gas Behaviour in Water Reactor Fuels

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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)

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Book Synopsis Fission Gas Behaviour in Water Reactor Fuels by :

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.

Thoria-based Nuclear Fuels

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Publisher : Springer Science & Business Media
ISBN 13 : 1447155890
Total Pages : 423 pages
Book Rating : 4.4/5 (471 download)

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Book Synopsis Thoria-based Nuclear Fuels by : Dasarathi Das

Download or read book Thoria-based Nuclear Fuels written by Dasarathi Das and published by Springer Science & Business Media. This book was released on 2013-12-24 with total page 423 pages. Available in PDF, EPUB and Kindle. Book excerpt: This 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.

Analysis of Transient Fission Gas Release and Swelling in Oxide Fuel

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Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Analysis of Transient Fission Gas Release and Swelling in Oxide Fuel by :

Download or read book Analysis of Transient Fission Gas Release and Swelling in Oxide Fuel written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Calculations of fission-gas behavior have been carried out with an updated version of the FRAS3 code for the FGR-40 series of transient tests of irradiated PNL-10 fuel. This same series of tests was used in an earlier evaluation study with a preliminay version of the code. While that study provided positive support for the modeling approach, it also indicated deficiencies in some areas. Although a number of improvements have been implemented in the current version of the code, this study examines the effect of an explicit treatment of bubble growth within the grains, including the effect of vacancy depletion caused by the competition of overpressured bubbles for available vacancies. The result is a reduction by as much as 90% in the predicted swelling, accompanied by an increase in transfer of gas from the grains to boundaries. Both swelling and gas release predictions are brought into much better agreement with the observed values.

Energy Research Abstracts

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ISBN 13 :
Total Pages : 660 pages
Book Rating : 4.:/5 (3 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 660 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Fission Gas Problem For Mobile Fuel Fast Reactors

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ISBN 13 :
Total Pages : 42 pages
Book Rating : 4.L/5 ( download)

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Book Synopsis The Fission Gas Problem For Mobile Fuel Fast Reactors by : Frederick G. Hammitt

Download or read book The Fission Gas Problem For Mobile Fuel Fast Reactors written by Frederick G. Hammitt and published by . This book was released on 1959 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 1082 pages
Book Rating : 4.0/5 ( download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-04 with total page 1082 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Comprehensive Nuclear Materials

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Publisher : Elsevier
ISBN 13 : 0081028660
Total Pages : 4871 pages
Book Rating : 4.0/5 (81 download)

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Book Synopsis Comprehensive Nuclear Materials by :

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Scientific and Technical Aerospace Reports

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ISBN 13 :
Total Pages : 1502 pages
Book Rating : 4.3/5 (243 download)

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Book Synopsis Scientific and Technical Aerospace Reports by :

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1969 with total page 1502 pages. Available in PDF, EPUB and Kindle. Book excerpt: Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.

Radioactive Waste Management

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ISBN 13 :
Total Pages : 622 pages
Book Rating : 4.X/5 (1 download)

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Book Synopsis Radioactive Waste Management by :

Download or read book Radioactive Waste Management written by and published by . This book was released on 1981 with total page 622 pages. Available in PDF, EPUB and Kindle. Book excerpt: