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The Possibility Of Continuous In Core Gaseous Extraction Of Volatile Fission Products In A Molten Fuel Reactor
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Book Synopsis The possibility of continuous in-core gaseous extraction of volatile fission products in a molten fuel reactor by : Mieczyslaw Taube
Download or read book The possibility of continuous in-core gaseous extraction of volatile fission products in a molten fuel reactor written by Mieczyslaw Taube and published by . This book was released on 1974 with total page 33 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 1974-07 with total page 978 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Experiments on the Release of Fission Products from Molten Reactor Fuels by : G. E. Creek
Download or read book Experiments on the Release of Fission Products from Molten Reactor Fuels written by G. E. Creek and published by . This book was released on 1959 with total page 38 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 1972 with total page 918 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Characterization of Fission Product Transport in a Gen. IV Gas-cooled Fast Reactor Plant Utilizing Vented Fuel by : Wesley Deason
Download or read book Characterization of Fission Product Transport in a Gen. IV Gas-cooled Fast Reactor Plant Utilizing Vented Fuel written by Wesley Deason and published by . This book was released on 2013 with total page 145 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant utilizing vented fuel has been characterized using analytical and computational methods. The goal was to increase current understanding of fission product transport in helium-cooled GFRs using vented fuel and to provide a toolset for determining issues which may arise during normal and abnormal operating conditions. A review of the Peach Bottom Unit 1 reactor, the Gas-Cooled Fast Reactor, the Gen IV Gas-Cooled Fast Reactor, and the Energy Multiplier Module--all helium-cooled nuclear systems utilizing vented fuel--provided sufficient background for understanding the design methodology behind vented system and helium purification system design. From documentation for these systems and other literature, the phenomena of fission product generation and decay, volatile fission product chemistry, fission product diffusion and release in fuel, fission product leakage through non-fuel components, fission product plateout, and collection of gaseous fission products through adsorption in the charcoal beds were identified as having a significant effect on the transport of fission products within a vented fuel system. Understanding of vented fuel system design and identified fission product transport phenomena was then used for the development of a vented fuel system model in the systems modeling program, STELLA. The model was used to analyze test cases, characterizing the time-dependent accumulation and decay of fission products in a vented fuel system. These results, used in conjunction with the review of past systems, were used to compile conclusions and recommendations for the design of vented fuel systems and helium purification systems, aiding direction of future research and design efforts. Briefly, the work found that the mass, activity, and power generation of accumulated fission products is likely to be very large, requiring significant consideration within the overall plant design. Additionally, the reduction of the source of vented fission products being purged from the primary vessel, either by fuel or core design, may present significant advantages in plant design. It was also found that safety systems will be necessary to prevent overheat and possible release from the helium purification system in the case of an accident scenario. Lastly, it was found that the determination of the purge stream leakage rate into the primary coolant and the fuel release rate are of crucial importance for the safety and economy of a vented fuel system. This work was funded as part of a Nuclear Energy University Programs Grant from the Department of Energy.
Book Synopsis Fission Product Release and Transport in Liquid Metal Fast Breeder Reactors by : G. W. Keilholtz
Download or read book Fission Product Release and Transport in Liquid Metal Fast Breeder Reactors written by G. W. Keilholtz and published by . This book was released on 1969 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Accessions of Unlimited Distribution Reports by :
Download or read book Accessions of Unlimited Distribution Reports written by and published by . This book was released on 1974-07-12 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Release from BWR Fuel Under LOCA Conditions by :
Download or read book Fission Product Release from BWR Fuel Under LOCA Conditions written by and published by . This book was released on 1981 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
Book Synopsis The Effect of Volatile Fission Products on Fuel Motion Potential, for Postulated Nuclear Reactor Core Overheating Accidents by : Paul Sasa
Download or read book The Effect of Volatile Fission Products on Fuel Motion Potential, for Postulated Nuclear Reactor Core Overheating Accidents written by Paul Sasa and published by . This book was released on 1979 with total page 287 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Calculations on the Gaseous and Volatile Fission Products in Highly Irradiated Nuclear Fuel by : A. J. Brook
Download or read book Calculations on the Gaseous and Volatile Fission Products in Highly Irradiated Nuclear Fuel written by A. J. Brook and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Molten Salt Reactors and Thorium Energy by : Thomas James Dolan
Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts Covers MSR applications, technical issues, reactor types and reactor designs Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe
Book Synopsis Government Reports Annual Index by :
Download or read book Government Reports Annual Index written by and published by . This book was released on 1989 with total page 1364 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nucleonics written by and published by . This book was released on 1955 with total page 1464 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission-product Release from TRIGA-LEU Reactor Fuels by :
Download or read book Fission-product Release from TRIGA-LEU Reactor Fuels written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The release of fission products, both gaseous and volatile metals, from TRIGA fuel is important for the analysis of possible accident conditions related to reactor operation and the design of future TRIGA fuel systems. Because of present national concerns over nuclear proliferation, it has become clear that future reactor fuels will, of necessity, utilize low-enriched uranium (LEU, enrichment
Download or read book Proceedings written by and published by . This book was released on 1959 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Experiments on the Release of Fission Products from Molten Reactor Fuels by :
Download or read book Experiments on the Release of Fission Products from Molten Reactor Fuels written by and published by . This book was released on 1958 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 d C in air or steam effected the release of 50% of the rare gases, 33% of the iodine, 9% of ihe cesium, and traces of strontiuun. After 25% burn-up, the cesiuun value increased to about 60%. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 d C released up to 2% of the iodine, 10% of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15% burn-up, when melted at 1850 d C, released up to 95% of the rare gases, 90% of the cesium, 60% of the iodine, and only a trace of strontiuun. (auth).
