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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.
Workshop
Sunday, September 25, 2022|1:00–5:00PM PDT|Grand Pacific AB
ADVANTG is a software package that generates variance reduction parameters (space- and energy-dependent weight windows and biased source probabilities) that can substantially improve the convergence rate of fixed-source neutron and photon radiation transport simulations using MCNP. ADVANTG implements the Consistent Adjoint Driven Importance Sampling (CADIS) method to accelerate individual tallies and the Forward-Weighted CADIS (FW-CADIS) method to obtain nearly uniform statistical precision across multiple tallies and large mesh tallies. Additionally, ADVANTG 3.2.0 has the capability to produce variance reduction parameters based on the Multi Step CADIS (MS-CADIS) methodology for optimal calculations of delayed gamma radiation fields such as the shutdown dose rate (SDDR) in fusion facilities.
The workshop will discuss the theoretical background of the methods implemented in ADVANTG before moving on to a demonstration of the use of CADIS and FW-CADIS methods on test cases. The workshop will also include a tutorial on how to visualize the discretized geometry, source and discrete ordinates solutions using the open-source VisIt software (https://wci.llnl.gov/codes/visit/). Common issues when using variance reduction will be discussed alongside some best practices and suggestions for ADVANTG workflows.
ADVANTG has been used in a variety of radiation transport applications at ORNL as well as other organizations. Some recent advanced applications will be presented and discussed, including the use of ADVANTG for pressure vessel fluence predictions, neutron fluence and radiation heating in LWR concrete bioshields, and in the workflow for determining SDDR in the JET and ITER fusion facilities.
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