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Author : M. H. Wood
Publisher :
ISBN 13 :
Total Pages : 34 pages
Book Rating : 4.:/5 (865 download)
Download or read book Factors Influencing Fission Gas Release and Swelling in Nuclear Fuels written by M. H. Wood and published by . This book was released on 1976 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Nathan Christopher Andrews
Publisher :
ISBN 13 :
Total Pages : 149 pages
Book Rating : 4.:/5 (824 download)
Download or read book Development of Fission Gas Swelling and Release Models for Metallic Nuclear Fuels written by Nathan Christopher Andrews and published by . This book was released on 2012 with total page 149 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel 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 : 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 : J.W. Harrison
Publisher :
ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (898 download)
Download or read book A Combined Fission Gas Release and Swelling Model for Fuel During Irradiation written by J.W. Harrison and published by . This book was released on 1981 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Hastings, I. J. (Ian James)
Publisher : Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN 13 :
Total Pages : 39 pages
Book Rating : 4.:/5 (158 download)
Download or read book A Microstructure-dependent Model for Fission Product Gas Release and Swelling in UO↓2 Fuel written by Hastings, I. J. (Ian James) and published by Chalk River, Ont. : Chalk River Nuclear Laboratories. This book was released on 1979 with total page 39 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 : M. H. Wood
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.:/5 (865 download)
Download or read book Modelling Fission Gas Release and Swelling in Fast Reactor Fuel Pins written by M. H. Wood and published by . This book was released on 1975 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. J. F. Notley
Publisher :
ISBN 13 :
Total Pages : 39 pages
Book Rating : 4.:/5 (158 download)
Download or read book A Microstructure-dependent Model for Fission Product Gas Release and Swelling in UO2 Fuel written by M. J. F. Notley and published by . This book was released on 1979 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Daniel Lee DeForest
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (277 download)
Download or read book Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications written by Daniel Lee DeForest and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to investigate whether fission gas swelling and release would be significant factors in a space based nuclear reactor operating under the Strategic Defense Initiative (SDI) program, the finite element program REDSTONE (Routine for Evaluating Dynamic Swelling in Transient Operational Nuclear Environments) was developed to model the 1-D, spherical geometry diffusion equations describing transient fission gas behavior in a single uranium nitride fuel grain. The equations characterized individual bubbles, rather than bubble groupings. This limited calculations to those scenarios where low temperatures, low burnups, or both were present. Instabilities in the bubble radii calculations forced the implementation of additional constraints limiting the bubble sizes to minimum and maximum (equilibrium) radii. The validity of REDSTONE calculations were checked against analytical solutions for internal consistency and against experimental studies for agreement with swelling and release results. These checks indicated that REDSTONE was satisfactorily accounting for the intragranular fission gas portion of swelling, but that other non-gaseous sources accounted for up to 1.5% additional swelling. A calculation was performed to determine the swelling and gas release associated with a hypothetical SDI scenario. The SDI scenario involved 10 years of low power operation at 10 kW followed by a 30 second rise to 1 MW which was maintained for approximately 15 minutes. The results indicated that the fuel pellet diametral increase would remain less than 1% and release would be negligible, far below that needed for design failure. This same scenario was run at higher temperatures to see if uncertainties in the operating parameters could cause significantly different results. It was apparent that further investigations into the swelling behavior near 1800°K were needed, as results indicated a significant shift to larger bubbles at this temperature. In an effort to understand the effect of property uncertainties on the solution, several of the properties were varied and the results compared. The largest effects were observed from changes in the irradiation enhanced diffusion coefficient and the resolution parameter. The resolution parameter uncertainty would have the largest potential effect on results, likely resulting in a reduction in the swelling and a corresponding increase in release.
Author :
Publisher :
ISBN 13 :
Total Pages : 11 pages
Book Rating : 4.:/5 (94 download)
Download or read book Uncertainty and Sensitivity Analysis of Fission Gas Behavior in Engineering-scale Fuel Modeling written by and published by . This book was released on 2014 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The role of uncertainties in fission gas behavior calculations as part of engineering-scale nuclear fuel modeling is investigated using the BISON fuel performance code and a recently implemented physics-based model for the coupled fission gas release and swelling. Through the integration of BISON with the DAKOTA software, a sensitivity analysis of the results to selected model parameters is carried out based on UO2 single-pellet simulations covering different power regimes. The parameters are varied within ranges representative of the relative uncertainties and consistent with the information from the open literature. The study leads to an initial quantitative assessment of the uncertainty in fission gas behavior modeling with the parameter characterization presently available. Also, the relative importance of the single parameters is evaluated. Moreover, a sensitivity analysis is carried out based on simulations of a fuel rod irradiation experiment, pointing out a significant impact of the considered uncertainties on the calculated fission gas release and cladding diametral strain. The results of the study indicate that the commonly accepted deviation between calculated and measured fission gas release by a factor of 2 approximately corresponds to the inherent modeling uncertainty at high fission gas release. Nevertheless, higher deviations may be expected for values around 10% and lower. Implications are discussed in terms of directions of research for the improved modeling of fission gas behavior for engineering purposes.
Author : Hubert C. Gibson
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (865 download)
Download or read book Gaseous Swelling and Release in Nuclear Fuels During Grain Growth written by Hubert C. Gibson and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A model of the generation and release of fission gas, as well as the total swelling over time, was created. It uses an ideal spherical fuel grain with a time-dependent radius. UO2 and quasi-homogeneous SBR MOX fuels were simulated with this model, and the results were compared to a fixed grain radius model of gaseous swelling. Gaseous swelling and fission gas release were calculated for temperatures from 1600 K to 2200 K. The grain growth of UO2 was found to decrease the time needed to saturate the intergranular boundaries as compared to simple diffusion without grain growth. Small temperatures increased the time required for saturation, as did small rates of grain growth. Gaseous swelling was within the range of values found by experimental data.
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Download or read book Fission Gas Induced Fuel Swelling in Low and Medium Burnup Fuel During High Temperature Transients. [PWR]. written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The behavior of light water reactor fuel elements under postulated accident conditions is being studied by the EG and G Idaho, Inc., Thermal Fuels Behavior Program for the Nuclear Regulatory Commission. As a part of this program, unirradiated and previously irradiated, pressurized-water-reactor type fuel rods were tested under power-cooling-mismatch (PCM) conditions in the Power Burst Facility (PBF). During these integral in-reactor experiments, film boiling was produced on the fuel rods which created high fuel and cladding temperatures. Fuel rod diameters increased in the film boiling region to a greater extent for irradiated rods than for unirradiated rods. The purpose of the study was to investigate and assess the fuel swelling which caused the fuel rod diameter increases and to evaluate the ability of an analytical code, the Gas Release and Swelling Subroutine - Steady-State and Transient (GRASS-SST), to predict the results.
Author : Daniel Lee DeForest
Publisher :
ISBN 13 :
Total Pages : 466 pages
Book Rating : 4.:/5 (277 download)
Download or read book Transient Fission Gas Behavior in Uranium Nitride Fuel Under Proposed Space Applications written by Daniel Lee DeForest and published by . This book was released on 1991 with total page 466 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Ralph O. Meyer
Publisher :
ISBN 13 :
Total Pages : 78 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 78 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Moustafa S. El-Koliel
Publisher :
ISBN 13 :
Total Pages : 25 pages
Book Rating : 4.:/5 (84 download)
Download or read book In Pile-fission Gas Release and Swelling of UO2 Fuel in Light Water Reactors written by Moustafa S. El-Koliel and published by . This book was released on 1999 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Moustafa S. El-Koliel
Publisher :
ISBN 13 :
Total Pages : 25 pages
Book Rating : 4.:/5 (247 download)
Download or read book In Pile-fission Gas Release and Swelling of UO 2 Fuel in Light Water Reactor written by Moustafa S. El-Koliel and published by . This book was released on 1999 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Atomic Energy of Canada Limited
Publisher :
ISBN 13 :
Total Pages : 39 pages
Book Rating : 4.:/5 (622 download)
Download or read book Microstructure-Dependent Model For Fission Product Gas Release and Swelling in Uo2 Fuel written by Atomic Energy of Canada Limited and published by . This book was released on 1977 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt:
