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Author : J. M. Kramer
Publisher :
ISBN 13 :
Total Pages : 21 pages
Book Rating : 4.:/5 (929 download)
Download or read book Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients written by J. M. Kramer and published by . This book was released on 1992 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 21 pages
Book Rating : 4.:/5 (727 download)
Download or read book Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients written by and published by . This book was released on 1992 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: Passive safety features in the metal-fueled Integral Fast Reactor (IFR) make it possible to avoid core damage for extended time periods even when automatic scram systems fail to operate or heat removal systems are severely degraded. The time scale for these transients are intermediate between those that have traditionally been analyzed in fast reactor safety assessments and those of normal operation. Consequently, it has been necessary to validate models and computer codes (FPIN2 and LIFE-METAL) for application to this time regime. Results from out-of-reactor Whole Pin Furnace tests are being used for this purpose. Pretest predictions for tests FM-1 through FM-6 have been performed and calculations have been compared with the experimental measurements.
Author : C. E Dickerman
Publisher :
ISBN 13 :
Total Pages : 102 pages
Book Rating : 4.3/5 (91 download)
Download or read book Studies of Fast Reactor Fuel Element Behavior Under Transient Heating to Failure written by C. E Dickerman and published by . This book was released on 1961 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt: Meltdown tests on single metallic un-irradiated fuel elements in TREAT are described. The fuel elements (EBRII, Mark I fuel pins, EBR-II fuel pins with refractory Nb or Ta cladding, and Fermi-1 fuel pins) are tested in an inert atmosphere, with no coolant. The fuel elements are exposed to reactor power bursts of 200 msec to 25 sec duration, under conditions simulating fast reactor operations. For these tests, the type of power burst, the integrated power, the fuel enrichment, the maximum cladding temperature, and the effects of the test on the fuel element are recorded.
Author : Aydin Karahan
Publisher :
ISBN 13 :
Total Pages : 344 pages
Book Rating : 4.:/5 (641 download)
Download or read book Modelling of Thermo-mechanical and Irradiation Behavior of Metallic and Oxide Fuels for Sodium Fast Reactors written by Aydin Karahan and published by . This book was released on 2009 with total page 344 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) The FEAST-OXIDE predictions has been compared to the available FFTF, EBR-II and JOYO databases, and the agreement between the code and data was found to be satisfactory. Both metal and oxide versions of FEAST are rather superior compared to many other fuel codes in the literature. Comparing metal and oxide versions, FEAST-OXIDE has a more sophisticated fission gas release and swelling model, which is based on vacancy flow. In addition, modeling of the chemistry module of the oxide fuel requires a much more detailed analysis to estimate its impact on the thermo-mechanical behavior with a reasonable accuracy. Finally, the melting of the oxide fuel and its effect on the thermo-mechanical performance have been modeled in case of transient scenarios.
Author :
Publisher :
ISBN 13 :
Total Pages : 25 pages
Book Rating : 4.:/5 (929 download)
Download or read book Irradiation Behavior of Metallic Fast Reactor Fuels written by and published by . This book was released on 1991 with total page 25 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.
Download or read book Behavior of Metallic Fuel in Treat Transient Overpower Tests written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Results and analyses are reported for TREAT in-pile transient overpower tests of margin to cladding failure and pre-failure axial expansion of metallic fuel. In all cases the power rise was exponential on an 8 s period until either incipient or actual cladding failure was achieved. Test fuel included EBR-II driver fuel and ternary alloy, the reference fuel of the Intergral Fast Reactor concept. Test pin burnup spanned the widest range available. The nature of the observed cladding failure and resultant fuel dispersals is described. Simple models are presented which describe observed cladding failures and pre-failure axial expansions yet are general enough to apply to all metal fuel types.
Author :
Publisher :
ISBN 13 :
Total Pages : 25 pages
Book Rating : 4.:/5 (727 download)
Download or read book Irradiation Behavior of Metallic Fast Reactor Fuels written by and published by . This book was released on 1991 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Metallic fuels were the first fuels chosen for liquid metal cooled fast reactors (LMR's). In the late 1960's world-wide interest turned toward ceramic LMR fuels before the full potential of metallic fuel was realized. However, during the 1970's the performance limitations of metallic fuel were resolved in order to achieve a high plant factor at the Argonne National Laboratory's Experimental Breeder Reactor II. The 1980's spawned renewed interest in metallic fuel when the Integral Fast Reactor (IFR) concept emerged at Argonne National Laboratory. A fuel performance demonstration program was put into place to obtain the data needed for the eventual licensing of metallic fuel. This paper will summarize the results of the irradiation program carried out since 1985.
Author : AYDIN KARAHAN
Publisher :
ISBN 13 : 9783838332772
Total Pages : 348 pages
Book Rating : 4.3/5 (327 download)
Download or read book Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors written by AYDIN KARAHAN and published by . This book was released on 2010-03 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 782 pages
Book Rating : 4.:/5 (319 download)
Download or read book Metals Abstracts written by and published by . This book was released on 1997 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 464 pages
Book Rating : 4.0/5 ( download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Modeling the Response of Fast Reactor Fuel to Accident Transients written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Progress in modeling the response of fast reactor fuel to accident transients is reported in four areas: fission gas release from grains and intragranular fuel swelling, fission gas redistribution and internal pressurization in solid fuel, fuel cracking models, and fuel plasticity modeling. Applications of models in the first two areas to assessment of the comparative dispersal potential of fuel in a CRBR hypothetical unprotected loss-of-flow accident with that in recent experiments are presented. It is concluded that the reactor case presents a greater dispersal potential.
Download or read book Review of Behavior of Mixed-oxide Fuel Elements in Extended Overpower Transient Tests in EBR-II. written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: From a series of five tests conducted in EBR-II, a substantial data base has been established on the performance of mixed-oxide fuel elements in a liquid-metal-cooled reactor under slow-ramp transient overpower conditions. Each test contained 19 preirradiated fuel elements with varying design and prior operating histories. Elements with aggressive design features, such as high fuel smear density and/or thin cladding, were included to accentuate transient effects. The ramp rates were either 0.1 or 10%[Delta]P/P/s and the overpowers ranged between[approx]60 and 100% of the elements' prior power ratings. Six elements breached during the tests, all with aggressive design parameters. The other elements, including all those with moderate design features for the reference or advanced long-life drivers for PNC's prototype fast reactor Monju, maintained their cladding integrity during the tests. Posttest examination results indicated that fuel/cladding mechanical interaction (FCMI) was the most significant mechanism causing the cladding strain and breach. In contrast, pressure loading from the fission gas in the element plenum was less important, even in high-burnup elements. During an overpower transient, FCMI arises from fuel/cladding differential thermal expansion, transient fuel swelling, and, significantly, the gas pressure in the sealed central cavity of elements with substantial centerline fuel melting. Fuel performance data from these tests, including cladding breaching margin and transient cladding strain, are correlatable with fuel-element design and operating parameters. These correlations are being incorporated into fuel-element behavior codes. At the two tested ramp rates, fuel element behavior appears to be insensitive to transient ramp rate and there appears to be no particular vulnerability to slow ramp transients as previously perceived.
Author : Marchetti, Marco
Publisher : KIT Scientific Publishing
ISBN 13 : 3731506114
Total Pages : 164 pages
Book Rating : 4.7/5 (315 download)
Download or read book Neutronics Methods for Transient and Safety Analysis of Fast Reactors written by Marchetti, Marco and published by KIT Scientific Publishing. This book was released on 2017-03-02 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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Publisher :
ISBN 13 :
Total Pages : 658 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 658 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 :
Total Pages : 640 pages
Book Rating : 4.:/5 (319 download)
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1977 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : United States. Energy Research and Development Administration. Technical Information Center
Publisher :
ISBN 13 :
Total Pages : 1680 pages
Book Rating : 4.3/5 (129 download)
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration. Technical Information Center and published by . This book was released on 1977 with total page 1680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
