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Thermal Release Of Volatile Fission Products From Irradiated Nuclear Fuel
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Book Synopsis Thermal Release of Volatile Fission Products from Irradiated Nuclear Fuel by :
Download or read book Thermal Release of Volatile Fission Products from Irradiated Nuclear Fuel written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An effective procedure for removing 3H, Xe and Kr from irradiated fuels was demonstrated using Shippingport UO2 fuel. The release characteristics of 3H, Kr, Xe, and I from irradiated nuclear fuel have been determined as a function of temperature and gaseous environment. Vacuum outgassing and a flowing gas stream have been used to vary the gaseous environment. Vacuum outgassing released about 99% of the 3H and 20% of both Kr and Xe within a 3 h at 1500°C. Similar results were obtained using a carrier gas of He containing 6% H2. However, a carrier gas containing only He resulted in the release of approximately 80% of the 3H and 99% of both Kr and Xe. These results indicate that the release of these volatile fission products from irradiated nuclear fuel is a function of the chemical composition of the gaseous environment. The rate of tritium release increased with increasing temperature (1100 to 1500°C) and with the addition of hydrogen to the gas stream. Using crushed UO2 fuel without cladding and He as the carrier gas, Kr was completely released at 1500°C in 2.5 h. Below 1350°C, no Kr-Xe release was observed. Approximately 86% of the 129I and 95% of the cesium was released from a piece (3.9 g) of UO2 fuel at 1500°C in He. The zirconium cladding was observed to fracture during heat treatment. A large-scale thermal outgassing system was conceptually designed by the General Atomic Company from an engineering analysis of available experimental data. The direct cost of a 0.5 metric/ton day thermal outgassing system is estimated to be $1,926,000 (1982 dollars), including equipment, installation, instrumentation and controls, piping, and services. The thermal outgassing process was determined to be a technically feasible and cost-competitive process to remove tritium in the head-end portion of a LWR fuel reprocessing plant. Additional laboratory-scale development has been recommended.
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 Release of Volatile Fission Products from Irradiated LWR Fuel by : I. Johnson
Download or read book Release of Volatile Fission Products from Irradiated LWR Fuel written by I. Johnson and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Release from Uranium by : R. K. Hilliard
Download or read book Fission Product Release from Uranium written by R. K. Hilliard and published by . This book was released on 1962 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Release from Irradiated Uranium-zirconium Hydride SNAP Fuel by : W. M. Cegelski
Download or read book Fission Product Release from Irradiated Uranium-zirconium Hydride SNAP Fuel written by W. M. Cegelski and published by . This book was released on 1964 with total page 46 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:
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 Release of Volatile Fission Products from Uranium Dioxide by : Dominique Bayen
Download or read book Release of Volatile Fission Products from Uranium Dioxide written by Dominique Bayen and published by . This book was released on 1983 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Release and transport behavior of volatile fission products in the sodium inpile loop fpl-2 by : H. Feuerstein
Download or read book Release and transport behavior of volatile fission products in the sodium inpile loop fpl-2 written by H. Feuerstein and published by . This book was released on 1984 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission product release from high burnup fuel during oxidation in air at 950 degrees c by : D. R. Mccracken
Download or read book Fission product release from high burnup fuel during oxidation in air at 950 degrees c written by D. R. Mccracken and published by . This book was released on 1985 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two mechanistically different regimes have been observed during the oxidation of uo2 in air: at temperatures greater than or equal to 800 degrees c, u3o8 forms large crystals which propagate in a front through the underlying u4o9/uo2; at temperatures less than 700 degrees c, one grain of uo2 ultimately gives one or more grains of u3o8. previous experiments (1) indicated that in this latter temperature zone, releases of fission products are low and probably originate from inventory at grain boundaries. the experiments described here at 950 degrees c using high burnup fuel (445, 465 mw.h/kg u) confirm earlier results obtained with low burnup fuel (2) at 920 degrees c: in this temperature zone, 100 percent of the volatile fission products are released when u3o8 is formed by oxidation of uo2 in air. within experimental error, oxidation rates and corresponding release rates are independent of burnup, so that data on oxidation rates obtained using unirradiated pellets can be used to estimate release rates of fission products during oxidation of irradiated fuel. iodine, in the form of i2, is released from the uranium matrix as readily as the noble gases, but subsequently adsorbs in steel pipework thus reducing its volatility in a real system. cs release was also observed. it lagged behind the iodine, ruling out csi as the volatile species.
Book Synopsis Nuclear Safety in Light Water Reactors by : Bal Raj Sehgal
Download or read book Nuclear Safety in Light Water Reactors written by Bal Raj Sehgal and published by Academic Press. This book was released on 2012-01-05 with total page 732 pages. Available in PDF, EPUB and Kindle. Book excerpt: La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.
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 Fission Product Processes In Reactor Accidents by : J. T. Rogers
Download or read book Fission Product Processes In Reactor Accidents written by J. T. Rogers and published by CRC Press. This book was released on 2020-12-17 with total page 883 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.
Book Synopsis Release of Volatile Fission Products from Lightly Irradiated Uranium Dioxide by : Lena Katrina Hansson
Download or read book Release of Volatile Fission Products from Lightly Irradiated Uranium Dioxide written by Lena Katrina Hansson and published by . This book was released on 1985 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Release of Fission Products from Irradiated Aluminide Fuel at High Temperature by :
Download or read book Release of Fission Products from Irradiated Aluminide Fuel at High Temperature written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiated uranium aluminide fuel plates of 40% U-235 enrichment were heated for the determination of fission products released under flowing helium gas at temperatures up to and higher than the melting point of fuel-cladding material. The release of fission products from the fuel plate at temperature below 500°C was found negligible. The firist rapid release of fission products was observed with the occurrence of blistering at 561 +- 1°C on the plates. The next release at 585°C might be caused by melting of the cladding material of 6061-Al alloy. The last release of fission product gases was occurred at the eutectic temperature of 640°C of U-Al(subscript x). The released material was mostly xenon, but small amounts of iodine and cesium were observed.
Book Synopsis A Physical Description of Fission Product Behavior Fuels for Advanced Power Reactors by :
Download or read book A Physical Description of Fission Product Behavior Fuels for Advanced Power Reactors written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Global Nuclear Energy Partnership (GNEP) is considering a list of reactors and nuclear fuels as part of its chartered initiative. Because many of the candidate materials have not been explored experimentally under the conditions of interest, and in order to economize on program costs, analytical support in the form of combined first principle and mechanistic modeling is highly desirable. The present work is a compilation of mechanistic models developed in order to describe the fission product behavior of irradiated nuclear fuel. The mechanistic nature of the model development allows for the possibility of describing a range of nuclear fuels under varying operating conditions. Key sources include the FASTGRASS code with an application to UO2 power reactor fuel and the Dispersion Analysis Research Tool (DART) with an application to uranium-silicide and uranium-molybdenum research reactor fuel. Described behavior mechanisms are divided into subdivisions treating fundamental materials processes under normal operation as well as the effect of transient heating conditions on these processes. Model topics discussed include intra- and intergranular gas-atom and bubble diffusion, bubble nucleation and growth, gas-atom re-solution, fuel swelling and?scion gas release. In addition, the effect of an evolving microstructure on these processes (e.g., irradiation-induced recrystallization) is considered. The uranium-alloy fuel, U-xPu-Zr, is investigated and behavior mechanisms are proposed for swelling in the [alpha]-, intermediate- and [gamma]-uranium zones of this fuel. The work reviews the FASTGRASS kinetic/mechanistic description of volatile?scion products and, separately, the basis for the DART calculation of bubble behavior in amorphous fuels. Development areas and applications for physical nuclear fuel models are identified.
Book Synopsis Release of Volatile Fission Products from UO2 by :
Download or read book Release of Volatile Fission Products from UO2 written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In our experiments, post-irradiation anneal of lightly-irradiated UO2 was used to measure the release kinetics of the volatile fission products Xe, I, and Te. The fraction of a particular fission product retained in a specimen was measured by gamma-ray spectroscopy before and following an anneal.
