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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.
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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
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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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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.
I. Hill, N. Soppera, M. Bossant
Nuclear Science and Engineering | Volume 178 | Number 3 | November 2014 | Pages 280-294
Technical Paper | doi.org/10.13182/NSE14-37
Articles are hosted by Taylor and Francis Online.
The 2014 International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook) spans over 30 000 pages and contains 136 evaluations. In the handbook, evaluations are grouped by reactor type (light water reactor, heavy water reactor, liquid metal cooled fast reactor, etc.) and contain up to ten different types of measurements, each of which can be applied to code and nuclear data validation. Despite the thoughtful organization and strict format rules for evaluations, identifying suitable validation cases remains challenging. To assist with searching and trending the IRPhEP Handbook, a relational database and user interface named IDAT (IRPhEP Database and Analysis Tool) was developed. IDAT was first distributed with the 2013 edition of the IRPhEP Handbook and will be updated annually as evaluations are added and revised. Data characterizing the measurements were extracted to allow for searching and trending in IDAT. Measurement types in the database include criticality, buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics, reaction rates, and power distribution measurements. Additionally, the database contains calculated quantities, such as neutron flux/capture/fission spectrum data, neutron balance data, and keff sensitivity data, along with tools to visualize these data. IDAT can employ data to assist in the identification of similar experiments using a variety of metrics, within a “Rank Similar” pane. For each measurement in the database, there is also a “Trending” pane, allowing multilevel plots of calculated over experimental values allowing users to drill down by applying various filters. This paper describes the creation of IDAT as well as its features.
