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High Density Dispersion Fuel
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Download or read book High Density Dispersion Fuel written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A fuel development campaign that results in an aluminum plate-type fuel of unlimited LEU burnup capability with an uranium loading of 9 grams per cm[sup 3] of meat should be considered an unqualified success. The current worldwide approved and accepted highest loading is 4.8 g cm[sup[minus]3] with U[sub 3]Si[sub 2] as fuel. High-density uranium compounds offer no real density advantage over U[sub 3]Si[sub 2] and have less desirable fabrication and performance characteristics as well. Of the higher-density compounds, U[sub 3]Si has approximately a 30% higher uranium density but the density of the U[sub 6]X compounds would yield the factor 1.5 needed to achieve 9 g cm[sup[minus]3] uranium loading. Unfortunately, irradiation tests proved these peritectic compounds have poor swelling behavior. It is for this reason that the authors are turning to uranium alloys. The reason pure uranium was not seriously considered as a dispersion fuel is mainly due to its high rate of growth and swelling at low temperatures. This problem was solved at least for relatively low burnup application in non-dispersion fuel elements with small additions of Si, Fe, and Al. This so called adjusted uranium has nearly the same density as pure[alpha]-uranium and it seems prudent to reconsider this alloy as a dispersant. Further modifications of uranium metal to achieve higher burnup swelling stability involve stabilization of the cubic[gamma] phase at low temperatures where normally[alpha] phase exists. Several low neutron capture cross section elements such as Zr, Nb, Ti and Mo accomplish this in various degrees. The challenge is to produce a suitable form of fuel powder and develop a plate fabrication procedure, as well as obtain high burnup capability through irradiation testing.
Book Synopsis Design and Fabrication of High Density Uranium Dispersion Fuels by :
Download or read book Design and Fabrication of High Density Uranium Dispersion Fuels written by and published by . This book was released on 1997 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Twelve different uranium alloys and compounds with uranium densities greater than 13.8 g/cc were fabricated into fuel plates. Sixty-four experimental fuel plates, referred to as microplates, with overall dimensions of 76.2 mm x 22.2 mm x 1.3 mm and elliptical fuel zone of nominal dimensions of 51 mm x 9.5 mm, began irradiation in the Advanced Test Reactor on August 23, 1997. The fuel test matrix consists of machined or comminuted (compositions are in weight%) U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6 Ru, 10Mo-0.05Sn, U2Mo and U3Si2(as a control). The low enriched (235U
Book Synopsis High Uranium Density Dispersion Fuel for the Reduced Enrichment of Research and Test Reactors Program by : Adam B. Robinson
Download or read book High Uranium Density Dispersion Fuel for the Reduced Enrichment of Research and Test Reactors Program written by Adam B. Robinson and published by . This book was released on 2007 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease the use of high enriched uranium in research and test reactors around the world, new fuels with high uranium densities must be developed such that low enrichment fuel may be used in its place. Preliminary studies on uranium molybdenum alloys have shown promising results. A uranium molybdenum fuel phase dispersed in a zirconium matrix is proposed and examined in this thesis. Work described herein includes the successful fabrication of materials, preparation of samples, diffusion testing, fuel fabrication, and analysis of the resulting product. The fabrication results appear to be very good and all data collected indicates that this fuel type is fabricable and justifies irradiation testing.
Book Synopsis Dispersion Fuel Elements by : Abe Noel Holden
Download or read book Dispersion Fuel Elements written by Abe Noel Holden and published by . This book was released on 1967 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Prospects of Stable High-density Dispersion Fuels by :
Download or read book Prospects of Stable High-density Dispersion Fuels written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The majority of research and test reactors around the world employ aluminum fuel element designs that contain dispersed powders of uranium compounds as fuel. Specifically, two compounds are used: (1) uranium oxide (U3O) and (2) an uranium aluminide mixed phase composed of the intermetallic compounds UAl2, UAl3, and UAl4, all made with highly enriched uranium (HEU), i.e., 93% 235U. The reduction of 235U enrichment to below 20%, to so-called low enriched uranium (LEU), requires the use of higher density fuels for those applications where increased fuel loading is not feasible. Fuel dispersant loading is, in practice, limited to approximately 45 vol %. Fuel development in the Reduced Envichment Research and Test Reactors (RERTR) program has focused on uranium silicides (U3Si and U3Si2) as the most promising high-density fuels. The compounds of U6Fe and U6Mn as well as U3Si containing Cu were tested as part of the search for stable very-high-density fuels. The problem of breakaway swelling in high-density fuel compounds is attributed to radiation-induced amorphization of these compounds. Alloy additions are a possible means by which the crystal structure of very-high-density compounds can be strengthened and preserved to high irradiation doses. Tailoring metallurgical treatment during fabrication, to avoid thermodynamically weak compounds, appears promising for certain compound combinations. 5 refs., 2 figs.
Book Synopsis Out-of-pile Examination of the High Density U-Mo/AL Dispersion Fuel by : Nico Wieschalla
Download or read book Out-of-pile Examination of the High Density U-Mo/AL Dispersion Fuel written by Nico Wieschalla and published by . This book was released on 2006 with total page 89 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Relative Neutronic Performance of Proposed High-density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors by :
Download or read book Relative Neutronic Performance of Proposed High-density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors written by and published by . This book was released on 1996 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper provides an overview of the neutronic performance of an idealized research reactor using several high density LEU fuels that are being developed by the RERTR program. High-density LEU dispersion fuels are needed for new and existing high-performance research reactors and to extend the lifetime of fuel elements in other research reactors. This paper discusses the anticipated neutronic behavior of proposed advanced fuels containing dispersions of U3Si2, UN, U2Mo and several uranium alloys with Mo, or Zr and Nb. These advanced fuels are ranked based on the results of equilibrium depletion calculations for a simplified reactor model having a small H2O-cooled core and a D2O reflector. Plans have been developed to fabricate and irradiate several uranium alloy dispersion fuels in order to test their stability and compatibility with the matrix material and to establish practical loading limits.
Book Synopsis Postirradiation Examination of High-density Uranium Alloy Dispersion Fuels by :
Download or read book Postirradiation Examination of High-density Uranium Alloy Dispersion Fuels written by and published by . This book was released on 1998 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two irradiation test vehicles, designated RERTR-1 and RERTR-2, were inserted into the Advanced Test Reactor in Idaho in August 1997. These tests were designed to obtain irradiation performance information on a variety of potential new, high-density uranium alloy dispersion fuels, including U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru and U-10Mo-0.05Sn; the intermetallic compounds U2Mo and U3Si2 were also included in the fuel test matrix. These fuels are included in the experiments as ''microplates'' (76 mm x 22 mm x 1.3 mm outer dimensions) with a nominal fuel volume loading of 25% and irradiated at relatively low temperature ((approximately) 100 C). RERTR-1 and RERTR-2 were discharged from the reactor in November 1997 and July 1998, respectively, at calculated peak fuel burnups of 45 and 71 at.%-U235. Both experiments are currently under examination at the Alpha Gamma Hot Cell Facility at Argonne National Laboratory in Chicago. This paper presents the postirradiation examination results available to date from these experiments.
Book Synopsis Irradiation Testing of High Density Uranium Alloy Dispersion Fuels by :
Download or read book Irradiation Testing of High Density Uranium Alloy Dispersion Fuels written by and published by . This book was released on 1997 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two irradiation test vehicles have been designed, fabricated, and inserted into the Advanced Test Reactor in Idaho. Irradiation of these experiments began in August 1997. These irradiation tests were designed to obtain irradiation performance information on a variety of potential new, high-density dispersion fuels. Each of the two irradiation vehicles contains 32 microplates. Each microplate is aluminum clad, having an aluminum matrix phase and containing one of the following compositions as the fuel phase: U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru, U-10Mo-0.05Sn, U2Mo, or U3Si2. These experiments will be discharged at peak fuel burnups of 40% and 80%. Of particular interest is the fission gas retention/swelling characteristics of these new fuel alloys. This paper presents the design of the irradiation vehicles and the irradiation conditions.
Book Synopsis Prototypic Irradiation Testing of High-density U-Mo Alloy Dispersion Fuels by :
Download or read book Prototypic Irradiation Testing of High-density U-Mo Alloy Dispersion Fuels written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Study of Fast Reactor Fuel Transmutation in a Candidate Dispersion Fuel Design by :
Download or read book A Study of Fast Reactor Fuel Transmutation in a Candidate Dispersion Fuel Design written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Dispersion fuels represent a significant departure from typical ceramic fuels to address swelling and radiation damage in high burnup fuel. Such fuels use a manufacturing process in which fuel particles are encapsulated within a non-fuel matrix. Dispersion fuels have been studied since 1997 as part of an international effort to develop and test very high density fuel types for the Reduced Enrichment for Research and Test Reactors (RERTR) program.[1] The Idaho National Laboratory is performing research in the development of an innovative dispersion fuel concept that will meet the challenges of transuranic (TRU) transmutation by providing an integral fission gas plenum within the fuel itself, to eliminate the swelling that accompanies the irradiation of TRU. In this process, a metal TRU vector produced in a separations process is atomized into solid microspheres. The dispersion fuel process overcoats the microspheres with a mixture of resin and hollow carbon microspheres to create a TRUC. The foam may then be heated and mixed with a metal power (e.g., Zr, Ti, or Si) and resin to form a matrix metal carbide, that may be compacted and extruded into fuel elements. In this paper, we perform reactor physics calculations for a core loaded with the conceptual fuel design. We will assume a "typical" TRU vector and a reference matrix density. We will employ a fuel and core design based on the Advanced Burner Test Reactor (ABTR) design.[2] Using the CSAS6 and TRITON modules of the SCALE system [3] for preliminary scoping studies, we will demonstrate the feasibility of reactor operations. This paper will describe the results of these analyses.
Book Synopsis Impact of Fuel Density on Performance and Economy of Research Reactors by : IAEA
Download or read book Impact of Fuel Density on Performance and Economy of Research Reactors written by IAEA and published by International Atomic Energy Agency. This book was released on 2021-04-22 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
Book Synopsis Medical Isotope Production Without Highly Enriched Uranium by : National Research Council
Download or read book Medical Isotope Production Without Highly Enriched Uranium written by National Research Council and published by National Academies Press. This book was released on 2009-06-27 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.
Book Synopsis High Density Fuel Development for Research Reactors by :
Download or read book High Density Fuel Development for Research Reactors written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An international effort to develop, qualify, and license high and very high density fuels has been underway for several years within the framework of multi-national RERTR programs. The current development status is the result of significant contributions from many laboratories, specifically CNEA in Argentina, AECL in Canada, CEA in France, TUM in Germany, KAERI in Korea, VNIIM, RDIPE, IPPE, NCCP and RIARR in Russia, INL, ANL and Y-12 in USA. These programs are mainly engaged with UMo dispersion fuels with densities from 6 to 8 gU/cm3 (high density fuel) and UMo monolithic fuel with density as high as 16 gU/cm3 (very high density fuel). This paper, mainly focused on the French & US programs, gives the status of high density UMo fuel development and perspectives on their qualification.
Book Synopsis Irradiation Testing of Intermediate and High-density U-Mo Alloy Dispersion Fuels to High Burnup by :
Download or read book Irradiation Testing of Intermediate and High-density U-Mo Alloy Dispersion Fuels to High Burnup written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dispersion Fuels for Advanced Organic Moderated Reactor by : J. Kroehler
Download or read book Dispersion Fuels for Advanced Organic Moderated Reactor written by J. Kroehler and published by . This book was released on 1960 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Design of High Density Gamma-phase Uranium Alloys for LEU Dispersion Fuel Applications by :
Download or read book Design of High Density Gamma-phase Uranium Alloys for LEU Dispersion Fuel Applications written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Uranium alloys are candidates for the fuel phase in aluminum matrix dispersion fuels requiring high uranium loading. Certain uranium alloys have been shown to have good irradiation performance at intermediate burnup. Previous studies have shown that acceptable fission gas swelling behavior and fuel-aluminum interaction is possible only if the fuel alloy can be maintained in the high temperature body-centered-cubic[gamma]-phase during fabrication and irradiation, i.e., at temperatures at which[alpha]-U is the equilibrium phase. Transition metals in Groups V through VIII are known to allow metastable retention of the gamma phase below the equilibrium isotherm. These metals have varying degrees of effectiveness in stabilizing the gamma phase. Certain alloys are metastable for very long times at the relatively low fuel temperatures seen in research reactor operation. In this paper, the existing data on the gamma stability of binary and ternary uranium alloys is analyzed. The mechanism and kinetics of decomposition of the gamma phase are assessed with the help of metal alloy theory. Alloys with the highest possible uranium content, good gamma-phase stability, and good neutronic performance are identified for further metallurgical studies and irradiation tests. Results from theory will be compared with experimentally generated data.
