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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Felix C. Difilippo, Stephen E. Fisher
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 310-324
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3176
Articles are hosted by Taylor and Francis Online.
Important decisions related to the kind of reactors to be used for the disposition of the surplus weapons-grade plutonium are going to be based on calculations. Benchmarking computational methods in all aspects of the fuel cycle with measured data is then an obvious necessity. Analysis of public domain data reveals that the cycle-2 irradiation in the Quad Cities-1 boiling water reactor is the most recent U.S. destructive examination, involving the irradiation of five mixed-oxide (MOX) assemblies using 80 and 90% fissile Pu, quite close to weapons-grade Pu isotopic. Such measurements are rare, and they might be the only source of information to quantify differences in key neutronics parameters between high-fissile Pu systems and the well-characterized use of reactor-grade Pu. The pin neutronic performances for the UO2 and MOX fuels are compared with assembly-level calculation in which ~20% of the pins are MOX pins surrounded by UO2 pins. For MOX rods, HELIOS models the chains for the isotopes of uranium and plutonium reasonably well when compared with measured data at ~12 000 MWd/tonne. However, indications are that the amounts of heavier actinides are underpredicted. Measurements and calculations of the relative pin power distribution for the last few weeks of the irradiation and the burnup are fairly consistent. The critical effects of the contribution of the 0.296-eV resonance to the production of higher actinides and the destruction of 239Pu are discussed.