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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
C. Muirhead, H. Li, K. Pilatzke, M. Byers, R. Carson, H. Boniface, S. Suppiah
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 281-285
Technical Paper | doi.org/10.1080/15361055.2017.1290974
Articles are hosted by Taylor and Francis Online.
Canadian Nuclear Laboratories (CNL) is developing a Proton Exchange Membrane-based (PEM) electrolyser intended for tritium removal. Commercially available Nafion® N-1110 membranes have been exposed to tritiated water (with a β activity of about 37 GBq/mL) prepared in the Tritium Facility at CNL. Three equivalent batches of Nafion® N-1110 membranes (each with a dimension of 4 cm × 4 cm) were exposed to β-doses of 67 kGy, 155 kGy, and 255 kGy, respectively.
The exposed membranes required decontamination for characterization and testing. A few different decontamination methods have been experimentally studied. These methods can be categorized as water elution and chemical soaking. The measured tritium concentration in eluent decreased quickly in the first 30 days of water elution, followed by a slow decay afterwards until reaching a plateau after about 100 days. Chemical soaking proved to be more effective than the water elution method and high temperature facilitated the tritium release.