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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
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.