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Nuclear Installations Safety
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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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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.
B. T. Rearden
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 367-382
Technical Paper | doi.org/10.13182/NSE03-03
Articles are hosted by Taylor and Francis Online.
Methodologies to calculate adjoint-based first-order-linear perturbation theory sensitivity coefficients with multigroup Monte Carlo methods are developed, implemented, and tested in this paper. These techniques can quickly produce sensitivity coefficients for all nuclides and reaction types for each region of a system model. Monte Carlo techniques have been developed to calculate the neutron flux moments and/or angular fluxes necessary for the generation of the scattering terms of the sensitivity coefficients.The Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in three dimensions (TSUNAMI-3D) control module has been written for the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system implementing this methodology. TSUNAMI-3D performs automated multigroup cross-section processing and then generates the forward and adjoint neutron fluxes with an enhanced version of the KENO V.a Monte Carlo code that implements the flux moment and angular flux calculational techniques. Sensitivity coefficients are generated with the newly developed Sensitivity Analysis Module for SCALE (SAMS). Results generated with TSUNAMI-3D compare favorably with results generated with direct perturbation techniques.