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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
L. San-Felice, R. Eschbach, P. Bourdot
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 217-232
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-121
Articles are hosted by Taylor and Francis Online.
The DARWIN package, developed by the CEA and its French partners (AREVA and EDF), provides the parameters required for fuel cycle applications: fuel inventory; decay heat; activity; neutron, gamma, alpha, and beta sources and spectra; and radiotoxicity. This paper presents the DARWIN2.3 experimental validation for fuel inventory and decay heat calculations on pressurized water reactors (PWRs). To validate this code system for spent fuel inventory, a large program has been undertaken, based on spent fuel chemical assays. This paper deals with the experimental validation of DARWIN2.3 for PWR uranium oxide and mixed oxide (MOX) fuel inventory calculation, focused on the isotopes involved in burnup credit applications and decay heat computations. The calculation-to-experiment ratio [(C - E)/1] discrepancies are calculated with the latest European evaluation file JEFF-3.1.1 associated with the Santamarina-Hfaiedh energy mesh. An overview of the tendencies is obtained on a complete range of burnup from 10 to 85 GWd/tonne (10 to 60 GWd/tonne for MOX fuel). The experimental validation of the DARWIN2.3 package for decay heat calculation is performed using calorimetric measurements carried out at the Swedish interim spent fuel storage facility, Clab, for PWR assemblies, covering large burnup (20 to 50 GWd/tonne) and cooling time (10 to 30 year) ranges.
