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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Fusion Science and Technology
Latest News
Disa seeks NRC license for its uranium mine waste remediation tech
The Nuclear Regulatory Commission has received a license application from Disa Technologies to use high-pressure slurry ablation (HPSA) technology for remediating abandoned uranium mine waste at inactive mining sites. Disa’s headquartersin are Casper, Wyo.
Kuo Tian, Frederik Arbeiter, Volker Heinzel, Keitaro Kondo, Martin Kubaschewski, Martin Mittwollen, Anton Möslang
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 245-251
Technical Paper | doi.org/10.13182/FST13-758
Articles are hosted by Taylor and Francis Online.
As the core region of IFMIF, the test cell (TC) suffers intense neutron and gamma irradiations. Major material challenges of the TC faced during engineering design phase are outlined and the current key material allocations are described. Actively cooled magnetite concrete is selected as the major biological shielding material for the TC, and actively cooled closed liner made of 316L stainless steel is selected to cover the complete TC internal surfaces. Material selections for sealing gaskets and electric insulations inside the TC are preliminarily defined based on dose rate maps at different locations. Metal based sealing gaskets and glass/ceramic electric insulations are applied in the areas with high dose rate, while organic based gaskets and conventional insulation materials can only be arranged behind sufficient biological shielding. Leak tight welding seams between removable interface shielding plugs and the TC liner are located in the region with very low helium generation rate (≪0.01 appm/fpy) in steel so that cutting and re-welding during the complete IFMIF life span is guaranteed.