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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
M. Gobien, R. Guo (NWMO)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 255-264
The Nuclear Waste Management Organization (NWMO) is responsible for the implementation of Adaptive Phased Management, the federally-approved plan for the safe long-term management of Canada’s used nuclear fuel. Under this plan, used nuclear fuel will ultimately be placed within a deep geological repository in a suitable host rock formation.
While a site has not yet been identified, NWMO conducts safety assessment studies for hypothetical sites to inform its siting and design programs. This paper presents an overview of a probabilistic assessment completed in support of the postclosure safety assessment evaluating the most recent container and placement concept for a hypothetical crystalline rock geosphere.
The probabilistic assessment consists of Monte Carlo simulations carried out using the system model SYVAC3-CC4 in which the full range of possible parameter values for the hundreds of distributed input parameters were explored. Unlike the deterministic assessment which test specific variations of the conservative Base Case, the probabilistic assessment uses the results from thousands of simulations and allows one to draw conclusions about model sensitivity as well as test the effects of inherent variability in the underlying model data.