Download or read book Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: For the current project to demonstrate that isotope ratio measurements can be extended to zirconium alloys used in LWR fuel assemblies we report new analyses on irradiated samples obtained from a reactor. Zirconium alloys are used for structural elements of fuel assemblies and for the fuel element cladding. This report covers new measurements done on irradiated and unirradiated zirconium alloys, Unirradiated zircaloy samples serve as reference samples and indicate starting values or natural values for the Ti isotope ratio measured. New measurements of irradiated samples include results for 3 samples provided by AREVA. New results indicate: 1. Titanium isotope ratios were measured again in unirradiated samples to obtain reference or starting values at the same time irradiated samples were analyzed. In particular, 49Ti/48Ti ratios were indistinguishably close to values determined several months earlier and to expected natural values. 2. 49Ti/48Ti ratios were measured in 3 irradiated samples thus far, and demonstrate marked departures from natural or initial ratios, well beyond analytical uncertainty, and the ratios vary with reported fluence values. The irradiated samples appear to have significant surface contamination or radiation damage which required more time for SIMS analyses. 3. Other activated impurity elements still limit the sample size for SIMS analysis of irradiated samples. The sub-samples chosen for SIMS analysis, although smaller than optimal, were still analyzed successfully without violating the conditions of the applicable Radiological Work Permit.
Download or read book The Determination of Uranium Burnup in Mwd ton written by and published by . This book was released on 1960 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear fuel is occasionally warranted to produce a stipulated average Mwd/ton for discharged fuel. Mwd/ton is defined as the megawatt days of heat produced per 2000 pounds of total fissionable and fertile isotopes initially present. In the history of nuclear power reactors, Mwd/ton has been a difficult number to measure accurately. Measurements performed in different laboratories are not always in agreement. A fuel burnup group is preparing tentative procedures which will help standardize the field of burnup analysis. The purpose of this report is to evaluate some of the existing methods for burnup analysis and to select, if possible, the one best suited for warranty purposes.
Download or read book Burnup Determination of Nuclear Fuels written by J. E. Rein and published by . This book was released on 1963 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Burnup Determination of Nuclear Fuels written by J. E. Rein and published by . This book was released on 1964 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Burnup Determination of Nuclear Fuels written by W. J. Maeck and published by . This book was released on 1965 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Burnup Determination of Nuclear Fuels written by W. J. Maeck and published by . This book was released on 1965 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Burnup Dependence of Light Water Reactor Spent Fuel Oxidation written by Brady Dean Hanson and published by . This book was released on 1998 with total page 474 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Burnup Determination of Nuclear Fuels Annual Progress Report written by and published by . This book was released on 1964 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proposed Determination of Nuclear Fuel Burnup Based on the Ration of Two Stable Fission Products of the Same Element written by William J. Maek and published by . This book was released on 1965 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Validation Work to Support the Idaho National Engineering and Environmental Laboratory Calculational Burnup Methodology Using Shippingport Light Water Breeder Reactor LWBR Spent Fuel Assay Data written by and published by . This book was released on 1999 with total page 81 pages. Available in PDF, EPUB and Kindle. Book excerpt: Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of-life (EOL) conditions for three fuel rods from different Light Water Breeder Reactor (LWBR) measurements. The three fuel rods evaluated here were taken from an LWBR seed module, a standard blanket module, and a reflector (Type IV) module. The calculated results were derived using a depletion methodology previously employed to evaluate many of the radionuclide inventories for spent nuclear fuels at the Idaho National Engineering and Environmental Laboratory. The primary goal of the calculational task was to further support the validation of this particular calculational methodology and its application to diverse reactor types and fuels. Result comparisons between the calculated and measured mass concentrations in the three rods indicate good agreement for the three major uranium isotopes (U-233, U-234, U-235) with differences of less than 20%. For the seed and standard blanket rod, the U-233 and U-234 differences were within 5% of the measured values (these two isotopes alone represent greater than 97% of the EOL total uranium mass). For the major krypton and xenon fission product isotopes, differences of less than 20% and less than 30% were observed, respectively. In general, good agreement was obtained for nearly all the measured isotopes. For these isotopes exhibiting significant differences, possible explanations are discussed in terms of measurement uncertainty, complex transmutations, etc.
Download or read book Methods for Determining Fuel Burnup written by R. L. Stover and published by . This book was released on 1961 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Methods for Determining Burnup in Enriched Uranium 235 Fuel Irradiated by Fast Reactor Neutrons written by Paul J. Richardson and published by . This book was released on 1971 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Guidebook on Non destructive Examination of Water Reactor Fuel written by and published by . This book was released on 1991 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: The guidebook gives a complete survey of non-destructive techniques available for application in the spent fuel pool as well as in hot cells, thereby supplementing an earlier publication, IAEA- TECDOC-245. It provides information on methods of examining water reactor fuel and a basis for further innovations.
Download or read book Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup written by and published by . This book was released on with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ATR WG MOX Fuel Pellet Burnup Measurement by Monte Carlo Mass Spectrometric Method written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper presents a new method for calculating the burnup of nuclear reactor fuel, the MCWO-MS method, and describes its application to an experiment currently in progress to assess the suitability for use in light-water reactors of Mixed-OXide (MOX) fuel that contains plutonium derived from excess nuclear weapons material. To demonstrate that the available experience base with Reactor-Grade Mixed uranium-plutonium OXide (RGMOX) can be applied to Weapons-Grade (WG)-MOX in light water reactors, and to support potential licensing of MOX fuel made from weapons-grade plutonium and depleted uranium for use in United States reactors, an experiment containing WG-MOX fuel is being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory. Fuel burnup is an important parameter needed for fuel performance evaluation. For the irradiated MOX fuel's Post-Irradiation Examination, the 148Nd method is used to measure the burnup. The fission product 148Nd is an ideal burnup indicator, when appropriate correction factors are applied. In the ATR test environment, the spectrum-dependent and burnup-dependent correction factors (see Section 5 for detailed discussion) can be substantial in high fuel burnup. The validated Monte Carlo depletion tool (MCWO) used in this study can provide a burnup-dependent correction factor for the reactor parameters, such as capture-to-fission ratios, isotopic concentrations and compositions, fission power, and spectrum in a straightforward fashion. Furthermore, the correlation curve generated by MCWO can be coupled with the 239Pu/Pu ratio measured by a Mass Spectrometer (in the new MCWO-MS method) to obtain a best-estimate MOX fuel burnup. A Monte Carlo - MCWO method can eliminate the generation of few-group cross sections. The MCWO depletion tool can analyze the detailed spatial and spectral self-shielding effects in UO2, WG-MOX, and reactor-grade mixed oxide (RG-MOX) fuel pins. The MCWO-MS tool only needs the MS-measured 239Pu/Pu ratio, without the measured isotope 148Nd concentration data, to determine the burnup accurately. MCWO-MS not only provided linear heat generation rate, Pu isotopic composition versus burnup, and burnup distributions within the WG-MOX fuel capsules, but also correctly pointed out the inconsistency in the large difference in burnups obtained by the 148Nd method.
Download or read book Application of Neutron Emission to the Determination of Burnup and Selected Isotope Contents in WWER 440 Reactor Fuel written by Pavel Liptak and published by . This book was released on 1991 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PROPOSED DETERMINATION OF NUCLEAR FUEL BURNUP BASED ON THE RATIO OF TWO STABLE FISSION PRODUCTS OF THE SAME ELEMENT written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
