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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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.
Yung-Shin Tseng, Chu Ching Hau, Jong-Rong Wang (NTHU), Po-Hsiu Lee, Chih-Tien Liu (Atomic Energy Council), Chunkuan Shih (NTHU)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 580-586
Since the Chloride-Induced Stress Corrosion Cracking (CI-SCC) has been attended in the Chinshan ISFSI project, the details of thermal information and humidity on the Transportable Storage Canister (TSC) becomes the valuable data for investigating the CISCC aging management. This is because that the temperature not only influenced the threshold of deliquescence but affected the growth rate of crack depth. Since the chloride salt only becomes deliquescent in specific situation depending on the site (e.g., the environment temperature and relative humidity) and cask (e.g., loading pattern and thermal load) condition of CSISFSI, which can be further evaluated by an applicable simulated methodology. In this study, a computational fluid dynamics (CFD), FLUENT, was utilized to investigate the temperature and considered the temperature with the relative humidity profile on each height of TSC shell of CSISFSI. A validated high-accuracy 2D model was developed to accelerate the simulation time due to the time scale of CISCC being up to 20 years. The result shows that the relative humidity will reduce as the temperature of TSC increases by decay heat of SNFs. For this reason, the maximum accumulated crack depth of the TSC will not exceed more than 0.36m height with 0.33mm/year, which is the maximum crack growth rate as the most conservative CaCl2 deliquescent threshold was assumed for prediction. Those quantized results not only prove that the re-inspection planning with 10 year period is enough to ensure the integrity of TSC but also provide a basis to reduce about 90% load for CSISFSI re-inspection work.