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Modeling The Response Of Fast Reactor Fuel To Accident Transients
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Book Synopsis Modeling the Response of Fast Reactor Fuel to Accident Transients by :
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.
Book Synopsis Neutronics Methods for Transient and Safety Analysis of Fast Reactors by : Marchetti, Marco
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:
Book Synopsis Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients by : J. M. Kramer
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:
Book Synopsis Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients by :
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 :United States. Energy Research and Development Administration. Technical Information Center Publisher : ISBN 13 : Total Pages :1682 pages Book Rating :4.3/5 (129 download)
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration. Technical Information Center
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 1682 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Survey of Current Methods for Analysis of Fast Reactor Transients Including Meltdown by : A. H. Kazi
Download or read book Survey of Current Methods for Analysis of Fast Reactor Transients Including Meltdown written by A. H. Kazi and published by . This book was released on 1964 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1977 with total page 646 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Analysis of Fast Reactor Transient Response and Safety in Selected Accidents by : D.G. Sherer
Download or read book An Analysis of Fast Reactor Transient Response and Safety in Selected Accidents written by D.G. Sherer and published by . This book was released on 1966 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois: Phenomenology by :
Download or read book Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois: Phenomenology written by and published by . This book was released on 1977 with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Probabilistic Transient Analysis of Fuel Choices for Sodium Fast Reactors by : Matthew R. Denman
Download or read book Probabilistic Transient Analysis of Fuel Choices for Sodium Fast Reactors written by Matthew R. Denman and published by . This book was released on 2011 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis presents the implications of using a risk-informed licensing framework to inform the design of Sodium Fast Reactors. NUREG-1860, more commonly known as the Technology Neutral Framework (TNF), is a risk-informed licensing process drafted by the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research. The TNF determines the acceptability of accident sequences by examining the 95th percentile estimate of both the frequency and quantity of radioactive material release and compares this value to predetermined limits on a Frequency-Consequence Curve. In order to apply this framework, two generic pool type sodium reactors, one using metal fuel and one using oxide fuel, were modeled in RELAP5-3D in order to determine the transient response of reactors to unprotected transient overpower and unprotected loss of flow events. Important transient characteristics, such as the reactivity coefficients, were treated as random variables which determine the success or failure of surviving the transient. In this context, success is defined as the cladding remaining intact and the avoidance of sodium boiling. In order to avoid running an excessive amount of simulations, the epistemic uncertainties around the random variables are sampled using importance sampling. For metallic fuel, the rate of fuel/cladding eutectic formation has typically been modeled as an Arrhenius process which depends only on the temperature of the fuel/cladding interface. Between the 1960s and the 1990s, numerous experiments have been conducted which indicate that the rate of fuel/cladding eutectic formation is more complex, depending upon fuel/cladding interfacial temperature, fuel constituents (uranium metal or uranium zirconium), cladding type (stainless steel 316, D9 or HT9), linear power, plutonium enrichment and burnup. This thesis improves the modeling accuracy of eutectic formation through the application of multivariable regression using a database of fuel/cladding eutectic experiments and determines that the remaining uncertainty governing the rate of eutectic formation should not significantly affect the frequency of cladding failure for tested cladding options. The general conclusion from this thesis is that when using NUREG-1860 to license metal or oxide fueled SFRs, it is steady state, not transient, cladding considerations which control optimal operating temperature, currently corresponding to an approximate core outlet temperature of 550°C. Metallic cores traditionally have been designed with core outlet temperatures of 510°C and increasing this temperature to 550°C may decrease the busbar cost by 19% when combined with the adoption of a Supercritical-CO2 power conversion cycle, reduced containment requirements, and Printed Circuit Heat Exchangers. While both fuel types will be shown to meet the NUREG-1860 requirements, the frequency of radiation release for unprotected loss of flow and unprotected transient overpower events for metallic fuel has been shown to be orders of magnitude lower than for oxide fuel.
Book Synopsis A Theoretical Model for Fast Reactor Transients Taking Into Account Fuel Pin Structure by : D. Martin
Download or read book A Theoretical Model for Fast Reactor Transients Taking Into Account Fuel Pin Structure written by D. Martin and published by . This book was released on 1978 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois: Licensing, safety-related design by :
Download or read book Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois: Licensing, safety-related design written by and published by . This book was released on 1977 with total page 542 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Finite Element Solution of the Nonlinear Coupled Neutronic-energy Equations for a Fast Reactor Fuel Cell by : Roy Edward Kasdorf
Download or read book Finite Element Solution of the Nonlinear Coupled Neutronic-energy Equations for a Fast Reactor Fuel Cell written by Roy Edward Kasdorf and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1967 with total page 1298 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-05 with total page 912 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois: Invited papers, panels, summary by :
Download or read book Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois: Invited papers, panels, summary written by and published by . This book was released on 1977 with total page 402 pages. Available in PDF, EPUB and Kindle. Book excerpt: