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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.
I. Soares, W. F. Miller, Jr., R. T. Perry
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 160-167
Technical Note | doi.org/10.13182/NSE93-A24028
Articles are hosted by Taylor and Francis Online.
The viability of the use of the ONEDANT discrete ordinates code for the calculation of the Doppler coefficient of reactivity for a pressurized water reactor is investigated. The ONEDANT results are compared with benchmark results from a Monte Carlo code, MCNP-3A. A comparison with the results obtained using the CELL-2 and WIMS-AECL codes is also included. The influences of certain variables, such as spatial mesh, SN angular quadrature order, interaction convergence criterion, boundary conditions, PN order, and number of energy groups, are analyzed. An alternative benchmark calculation to the Monte Carlo result is attempted to provide some feel for the approximate accuracy of the Monte Carlo calculation. Such an alternative answer is important when less approximate methods are compared with these results.
