Nondestructive, Energy-dispersive, X-ray Fluorescence Analysis of Actinide Stream Concentrations from Reprocessed Nuclear Fuels PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
In one plan for reprocessing LWR spent fuel, after separation from fission products and transplutonics, part of the U and all of the Pu in a nitrate solution will form a coprocessed stream which is then evaporated and sent to a hold tank for accounting. The remaining U fraction will be purified and sent to a separate storage tank. These two streams can be monitored using x-ray fluorescence analysis. This report discusses equipment, spectra, cell calibration, and dynamic concentration measurements. 7 figures. (DLC).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
In one plan for reprocessing LWR spent fuel, after separation from fission products and transplutonics, part of the U and all of the Pu in a nitrate solution will form a coprocessed stream which is then evaporated and sent to a hold tank for accounting. The remaining U fraction will be purified and sent to a separate storage tank. These two streams can be monitored using x-ray fluorescence analysis. This report discusses equipment, spectra, cell calibration, and dynamic concentration measurements. 7 figures. (DLC).
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Energy-dispersive x-ray fluorescence analysis (XRFA) can be used to measure nondestructively pure and mixed U/Pu concentrations in process streams and hold tank solutions. The 122-keV gamma ray from 57Co excites the actinide K x rays which are detected by a HPGe detector. A computer- and disk-based analyzer system provides capability for making on-stream analyses, and the noninvasive measurement is easily adapted directly to appropriate sized pipes used in a chemical reprocessing plant. Measurement times depend on concentration and purpose but vary from 100 to 500s for process control of strong to weak solutions. Accountability measurements require better accuracy thus more time; and for solutions containing plutonium, require a measurement of the solution radioactivity made with an automatic shutter that eclipses the two exciting sources. Plutonium isotopic abundances can also be obtained. Concentrations in single or dual element solutions from less than 1 g/l to over 200 g/l are determined to an accuracy of 0.2% after calibration of the system. For mixed solutions the unknown ratio of U to Pu is linearly related to the net U/Pu K x-ray intensities. Concentration values for ratios different than the calibration ratio require only small corrections to the values derived from a calibration polynomial. Minor fission product contamination does not prevent concentration determinations by XRFA. The computer-based system also allows real-time dynamic concentration measurements to be made.
Author: Donald O. Thompson Publisher: Springer Science & Business Media ISBN: 1461337062 Category : Technology & Engineering Languages : en Pages : 1818
Book Description
In this volume (parts 1 and 2) are contained the edited papers presented at the annual Review of Progress in Quantitative NDE held at the University of California, San Diego, August 1-6, 1982. This Review, possibly the most comprehensive annual symposium emphasizing both ongoing research and applications in quantitative NDE, was sponsored by the Center for Advanced NDE at the Ames Laboratory of the U. S. Department of Energy in cooperation with the Materials Laboratory of the Air Force Wright Aeronautical Laboratories and the Defense Advanced Research Projects Agency. Over 300 attendees representing various government agencies and the industrial and university communities participated in the technical presentations, poster sessions, and discussions. The symposium benefited from the insight of two keynote speak ers, Dr. Harris Burte of the Materials Laboratory, AFWAL, and Mr. Ward Rummel of the Martin Marietta Corporation, who presented complementary messages. Dr. Burte pointed out the need to identify "windows" to serve as guides for focusing NDE research. The "window" concept may be thought of as an opportunity for the application of NDE technology to an important problem and, through this application, to identify knowledge gaps which must be filled by generic research. This concept simultaneously provides a mechanism for the solution of a direct ap plication problem and a set of strong guidelines for generic research directions. Mr. Rummel called attention to the value of "lessons learned" from var.
Author: Publisher: ISBN: Category : Languages : en Pages : 16
Book Description
There is an urgent need for an instrument that can quickly measure the concentration of Plutonium and other Actinides mixed with Uranium in liquids containing dissolved spent fuel rods. Parallax Research, Incorporated proposes to develop an x-ray spectrometer capable of measuring U, Np and Pu in dissolved nuclear fuel rod material to less than 10 ppm levels to aid in material process control for these nuclear materials. Due to system noise produced by high radioactivity, previous x-ray spectrometers were not capable of low level measurements but the system Parallax proposed has no direct path for undesired radiation to get to the detector and the detector in the proposed device is well shielded from scatter and has very low dark current. In addition, the proposed spectrometer could measure these three elements simultaneously, also measuring background positions with an energy resolution of roughly 100 eV making it possible to see a small amount of Pu that would be hidden under the tail of the U peak in energy dispersive spectrometers. Another nearly identical spectrometer could be used to target Am and Cm if necessary. The proposed spectrometer needs only a tiny sample of roughly 1 micro-liter (1 mm3) and the measurement can be done with the liquid flowing in a radiation and chemical immune quartz capillary protected by a stainless steel rod making it possible to continuously monitor the liquid or to use a capillary manifold to measure other liquid streams. Unlike other methods such as mass spectroscopy where the sample must be taken to a remote facility and might take days for turn-around, the proposed measurement should take less than an hour. This spectrometer could enable near real-time measurement of U, Pu and Np in dilute dissolved spent nuclear fuel rod streams.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The energy-dispersive x-ray fluorescence analysis (XRFA) technique has been implemented at several spent nuclear fuel reprocessing facilities for nondestructive measurements of uranium and/or plutonium concentrations in process streams and product storage tanks. An important factor in these quantitative measurements is the absorption of the fluoresced x-rays by the solution matrix, which must be taken into account to accurately quantify the U or Pu concentrations. We describe a new, accurate method using a dual transmission source of Gd-153 and Co-57 to correct for matrix effects. Results of measurements on uranium and plutonium solution standards show the methodology to be better than 0.5%, which includes statistical precision, over the concentration range from 1 to 250 g/l. 5 refs., 4 figs., 3 tabs.
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Author: David Conrad Camp
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Author: Donald O. Thompson
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Author: Thomas R. Canada
Author: American Nuclear Society