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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
A. A. Argekar, S. K. Thulasidas, M. J. Kulkarni, M. K. Bhide, R. Sampathkumar, S. V. Godbole, V. C. Adya, B. A. Dhawale, B. Rajeshwari, Neelam Goyal, P. J. Purohit, A. G. Page, A. G. I. Dalvi, T. R. Bangia, M. D. Sastry, P. R. Natarajan
Nuclear Technology | Volume 84 | Number 2 | February 1989 | Pages 196-204
Technical Paper | Analyse | doi.org/10.13182/NT89-A34187
Articles are hosted by Taylor and Francis Online.
Uranium-aluminum alloys with a significant enrichment of uranium with 233U or 235U serve as nuclear fuels in research reactors. The quality assurance of this fuel requires, among other things, precise knowledge that all trace metal constituents that affect neutron economy, fuel integrity, and fuel fabrication process parameters are well within the specification limits. Trace metal characterization of 233U-Al alloy has been carried out by atomic spectrometry. The trace metal constituents of interest are grouped into common metals (silver, boron, calcium, cadmium, cobalt, chromium, copper, iron, magnesium, manganese, molybdenum, sodium, nickel, lead, silicon, tin, titanium, vanadium, tungsten, and zinc) and lanthanides (cerium, dysprosium, europium, gadolinium, holmium, lutetium, samarium, and terbium). The elements yttrium and zirconium are grouped with the latter in view of the chemical separation procedure used. The alloy samples are dissolved in 6 M HCl and evaporated to dryness with nitric acid, and the residue is ignited to oxide. The common metals other than silver are determined in the oxide samples using carrier excitation of the analyte spectra obtained using a computer-controlled multichannel direct reading spectrometer. Electrothermal atomization atomic absorption spectrometry is used for determining silver, using the nitric acid solution of the alloy. The rare earth elements yttrium and zirconium are determined after separation from the U-Al matrix, using a sequence of chemical procedures. In the first stage, uranium is separated by solvent extraction using a TnOA/xylene/HCl system and in the second stage aluminum is separated as sodium-aluminate. The trace elements are determined by a dc arc emission spectrographic method after chemical separation. Of these, dysprosium, europium, gadolinium, and samarium are determined by inductively coupled plasma-atomic emission spectrometry also. These methods are found to be quite adequate for the requirements of U-Al alloy fuel samples. Typical detection limits of these analytes varied in the 0.01-to 1.25-µg range. The precision varied in the 10 to 35% range. The waste generated in these processes has been treated for quantitative recovery of 233U.
