ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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May 2025
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.
Brian C. Kiedrowski, Forrest B. Brown
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 227-244
Technical Paper | doi.org/10.13182/NSE12-46
Articles are hosted by Taylor and Francis Online.
A continuous-energy Monte Carlo method is developed to compute adjoint-based k-eigenvalue sensitivity coefficients with respect to nuclear data. The method is implemented into MCNP6 and is based upon similar methodologies used to compute other adjoint-weighted quantities. The Monte Carlo tallies employed are explained. Verification of the method is performed by comparing results to analytic solutions, direct density perturbations, and those from other software packages such as TSUNAMI-3D and MONK. Results of analytic solutions agree within a few tenths of a percent. Direct density perturbations and comparisons with other software generally agree within a few percent.