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Dissolution Of Zircaloy 2 Clad Uo2 Commercial Reactor Fuel
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Book Synopsis Dissolution of Zircaloy 2 Clad UO2 Commercial Reactor Fuel by :
Download or read book Dissolution of Zircaloy 2 Clad UO2 Commercial Reactor Fuel written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The primary goal of this investigation was to evaluate the effectiveness of the chop-leach process, with nitric acid solvent, to produce a nominally 300 g/L [U] and 1 M [H] product solution. The results of this study show that this processing technique is appropriate for applications in which a low free acid and moderately high U content are desired. The 7.75 L of product solution, which was over 450 g/L in U, was successfully diluted to produce about 13 L of solvent extraction feed that was 302 g/L in U with a [H] in the range 0.8-1.2 M.A secondary goal was to test the effectiveness of this treatment for the removal of actinides from Zircaloy cladding to produce a low-level radioactive waste (LLW) cladding product. Analysis of the cladding shows that actinides are present in the cladding at a concentration of about 5000 [eta]Ci/g, which is about 50 times greater than the acceptable transuranium element limit in low level radioactive waste. It appears that the concentration of nitric acid used for this dissolution study (initial concentration 4 M, with 10 M added as the dissolution proceeded) was inadequate to completely digest the UO2 present in the spent fuel. The mass of insoluble material collected from the initial treatments with nitric acid, 340 g, was much higher than expected, and analysis of this insoluble residue showed that it contained at least 200 g U.
Book Synopsis An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels by : B. J. Newby
Download or read book An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels written by B. J. Newby and published by . This book was released on 1963 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Fuel Processing written by and published by . This book was released on 1965 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Validation of the olander model for uo2 dissolution in molten zircaloy-4 at 2000 degrees c by : P. J. Hayward
Download or read book Validation of the olander model for uo2 dissolution in molten zircaloy-4 at 2000 degrees c written by P. J. Hayward and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
Author :Atomic Energy of Canada Limited Publisher :Pinawa, Man. : Whiteshell Nuclear Research Establishment ISBN 13 : Total Pages :15 pages Book Rating :4.:/5 (16 download)
Book Synopsis The Dissolution of UO↓2 by Molten Zircaloy-4 Cladding by : Atomic Energy of Canada Limited
Download or read book The Dissolution of UO↓2 by Molten Zircaloy-4 Cladding written by Atomic Energy of Canada Limited and published by Pinawa, Man. : Whiteshell Nuclear Research Establishment. This book was released on 1985 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels by : B. J. Newby
Download or read book An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels written by B. J. Newby and published by . This book was released on 1963 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Zircex and Modified Zirflex Processes for Dissolution of 8% U-91% Zr-1% H TRIGA Reactor Fuel by : T. A. Gens
Download or read book Zircex and Modified Zirflex Processes for Dissolution of 8% U-91% Zr-1% H TRIGA Reactor Fuel written by T. A. Gens and published by . This book was released on 1961 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Study of Dissolution of Reactor Fuels Containing Zirconium in a Titanium Vessel by : Walter Ernest Clark
Download or read book A Study of Dissolution of Reactor Fuels Containing Zirconium in a Titanium Vessel written by Walter Ernest Clark and published by . This book was released on 1961 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior by : A. L. Geary
Download or read book Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior written by A. L. Geary and published by . This book was released on 1960 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution Process for ZrO.sub. 2 -UO.sub. 2 -CaO Fuels by :
Download or read book Dissolution Process for ZrO.sub. 2 -UO.sub. 2 -CaO Fuels written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The present invention provides an improved dissolution process for ZrO.sub. 2 -UO.sub. 2 -CaO-type pressurized water reactor fuels. The zirconium cladding is dissolved with hydrofluoric acid, immersing the ZrO.sub. 2 -UO.sub. 2 -CaO fuel wafers in the resulting zirconium-dissolver-product in the dissolver vessel, and nitric acid is added to the dissolver vessel to facilitate dissolution of the uranium from the ZrO.sub. 2 -UO.sub. 2 -CaO fuel wafers.
Download or read book Reactor fuel processing written by and published by . This book was released on 1965 with total page 580 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modified Zirflex Process for Dissolution of Zirconium-and Niobium-bearing Nuclear Fuels in Aqueous Fluoride Solutions by : T. A. Gens
Download or read book Modified Zirflex Process for Dissolution of Zirconium-and Niobium-bearing Nuclear Fuels in Aqueous Fluoride Solutions written by T. A. Gens and published by . This book was released on 1959 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid by :
Download or read book Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid written by and published by . This book was released on 1961 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution of Dresden Reactor Fuel by : G. F. Kessinger
Download or read book Dissolution of Dresden Reactor Fuel written by G. F. Kessinger and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Fuel Cycle Initiative (AFCI) program is being developed to address disposal of commercial nuclear fuel and improve the performance of the geologic repository. The primary goal of the present work was to demonstrate the use of the chop-leach process, with nitric acid dissolvent, to produce a feed solution for the UREX process . The secondary goal was to test the efficacy of this treatment for leaching actinides from Zircaloy cladding.
Book Synopsis Accident-Tolerant Materials for Light Water Reactor Fuels by : Raul B. Rebak
Download or read book Accident-Tolerant Materials for Light Water Reactor Fuels written by Raul B. Rebak and published by Elsevier. This book was released on 2020-01-10 with total page 237 pages. Available in PDF, EPUB and Kindle. Book excerpt: Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic. Introduces the fundamental description of accident tolerant fuel, including fabrication and implementation Describes both the benefits and detriments of the various Accident Tolerant Fuel concepts Includes information on the process of materials selection with a discussion of how and why specific materials were chosen, as well as why others failed
Book Synopsis Engineering Separations Unit Operations for Nuclear Processing by : Reid Peterson
Download or read book Engineering Separations Unit Operations for Nuclear Processing written by Reid Peterson and published by CRC Press. This book was released on 2019-11-15 with total page 261 pages. Available in PDF, EPUB and Kindle. Book excerpt: Engineering Separations Unit Operations for Nuclear Processing provides insight into the fundamentals of separations in nuclear materials processing not covered in typical texts. This book integrates fuel cycle and waste processing into a single, coherent approach, demonstrating that the principles from one field can and should be applied to the other. It provides historical perspectives on nuclear materials processing, current assessment and challenges, and how past challenges were overcome. It also provides understanding of the engineering principles associated with handling nuclear materials. This book is aimed at researchers, graduate students, and professionals in the fields of chemical engineering, mechanical engineering, nuclear engineering, and materials engineering.
Book Synopsis An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels by : K. L. Rohde
Download or read book An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels written by K. L. Rohde and published by . This book was released on 1962 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
