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Nitride Fuel Modeling Recommendation For Nitride Fuel Material Property Measurement Priority
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Book Synopsis Nitride Fuel Modeling Recommendation for Nitride Fuel Material Property Measurement Priority by : Richard Moore
Download or read book Nitride Fuel Modeling Recommendation for Nitride Fuel Material Property Measurement Priority written by Richard Moore and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this effort was to provide the basis for a model that effectively predicts nitride fuel behavior. Material property models developed for the uranium nitride fuel system have been used to approximate the general behavior of nitride fuels with specific property models for the transuranic nitride fuels utilized as they become available. The AFCI fuel development program now has the means for predicting the behavior of the transuranic nitride fuel compositions. The key data and models needed for input into this model include:Thermal conductivity with burnupFuel expansion coefficientFuel swelling with burnupFission gas release with burnup. Although the fuel performance model is a fully functional FEA analysis tool, it is limited by the input data and models.
Book Synopsis Reactor Fuels, Materials and Systems under Extreme Environments by : Wenzhong Zhou
Download or read book Reactor Fuels, Materials and Systems under Extreme Environments written by Wenzhong Zhou and published by Frontiers Media SA. This book was released on 2022-03-25 with total page 360 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications by : J. Ahn
Download or read book Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications written by J. Ahn and published by . This book was released on 2006 with total page 91 pages. Available in PDF, EPUB and Kindle. Book excerpt: The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy & Environment (E & amp;E) and Chemistry & Material Sciences (C & amp;MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E & E and C & MS Directorates co-sponsored this Laboratory Directed Research & Development (LDRD) Project on Mono-Uranium Nitride Fuel Development for SSTAR and Space Applications. In fact, three out of the six GEN-IV reactor concepts consider using the nitride-based fuel, as shown in Table 1. SSTAR is a liquid-metal cooled, fast reactor. It uses nitride fuel in a sealed reactor vessel that could be shipped to the user and returned to the supplier having never been opened in its long operating lifetime. This sealed reactor concept envisions no fuel refueling nor on-site storage of spent fuel, and as a result, can greatly enhance proliferation resistance. However, the requirement for a sealed, long-life core imposes great challenges to research and development of the nitride fuel and its cladding. Cladding is an important interface between the fuel and coolant and a barrier to prevent fission gas release during normal and accidental conditions. In fabricating the nitride fuel rods and assemblies, the cladding material should be selected based on its the coolant-side corrosion properties, the chemical/physical interaction with the nitride fuel, as well as their thermal and neutronic properties. The US NASA space reactor, the SP-100 was designed to use mono-uranium nitride fuel. Although the SP-100 reactor was not commissioned, tens of thousand of nitride fuel pellets were manufactured and lots of them, cladded in Nb-1-Zr had been irradiated in fast test reactors (FFTF and EBR-II) with good irradiation results. The Russian Naval submarines also use nitride fuel with stainless steel cladding (HT-9) in Pb-Bi coolant. Although the operating experience of the Russian submarine is not readily available, such combination of fuel, cladding and coolant has been proposed for a commercial-size liquid-metal cooled fast reactor (BREST-300). Uranium mono-nitride fuel is studied in this LDRD Project due to its favorable properties such as its high actinide density and high thermal conductivity. The thermal conductivity of mono-nitride is 10 times higher than that of oxide (23 W/m-K for UN vs. 2.3 W/m-K for UO{sub 2} at 1000 K) and its melting temperature is much higher than that of metal fuel (2630 C for UN vs. 1132 C for U metal). It also has relatively high actinide density, (13.51 gU/cm{sup 3} in UN vs. 9.66 gU/cm{sup 3} in UO{sub 2}) which is essential for a compact reactor core design. The objective of this LDRD Project is to: (1) Establish a manufacturing capability for uranium-based ceramic nuclear fuel, (2) Develop a computational capability to analyze nuclear fuel performance, (3) Develop a modified UN-based fuel that can support a compact long-life reactor core, and (4) Collaborate with the Nuclear Engineering Department of UC Berkeley on nitride fuel reprocessing and disposal in a geologic repository.
Book Synopsis Empirical Modeling of Uranium Nitride Fuels by : Daniel Edward Brozak
Download or read book Empirical Modeling of Uranium Nitride Fuels written by Daniel Edward Brozak and published by . This book was released on 1987 with total page 460 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 with total page 964 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 with total page 1036 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NBS Special Publication written by and published by . This book was released on 1968 with total page 752 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Publications of the National Bureau of Standards by : United States. National Bureau of Standards
Download or read book Publications of the National Bureau of Standards written by United States. National Bureau of Standards and published by . This book was released on 1976 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Publications of the National Institute of Standards and Technology ... Catalog by : National Institute of Standards and Technology (U.S.)
Download or read book Publications of the National Institute of Standards and Technology ... Catalog written by National Institute of Standards and Technology (U.S.) and published by . This book was released on 1977 with total page 746 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Publications of the National Bureau of Standards ... Catalog by : United States. National Bureau of Standards
Download or read book Publications of the National Bureau of Standards ... Catalog written by United States. National Bureau of Standards and published by . This book was released on 1977 with total page 748 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Publications by : United States. National Bureau of Standards
Download or read book Publications written by United States. National Bureau of Standards and published by . This book was released on 1977 with total page 766 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Publications of the National Bureau of Standards, 1976 Catalog by : United States. National Bureau of Standards
Download or read book Publications of the National Bureau of Standards, 1976 Catalog written by United States. National Bureau of Standards and published by . This book was released on 1977 with total page 742 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NASA SP. written by and published by . This book was released on 1993 with total page 360 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
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 1995 with total page 994 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Critical Review of Space Nuclear Power and Propulsion 1984-1993 by : Mohamed S. El-Genk
Download or read book A Critical Review of Space Nuclear Power and Propulsion 1984-1993 written by Mohamed S. El-Genk and published by American Institute of Physics. This book was released on 1994 with total page 488 pages. Available in PDF, EPUB and Kindle. Book excerpt: Market: Researchers in nuclear power, physicists, chemical and nuclear engineers, students, and policy makers. The papers in this volume summarize key technological advancements that occurred during the ten years from 1984 to 1993 in such areas as heat pipe technology, fuels, space nuclear safety, dynamic power conversion systems, and advanced radiator technologies for spacecraft power systems. In light of new industry initiatives to form a consortia and the possibility of bi-modal space nuclear power and propulsion systems, this informative volume will be an invaluable reference source.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993-12 with total page 526 pages. Available in PDF, EPUB and Kindle. Book excerpt:
