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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
Philipp Herold, Michael Jobmann (DBE Technology GmbH)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 758-766
Within the framework of the R&D project ANSICHT (Safety Assessment Methodology for a German High-level Waste Repository in Clay Formations), DBE TECHNOLOGY GmbH, BGR, and GRS developed an integrated methodological approach on how to demonstrate the safety of a HLW repository in claystone in Germany. One challenging aspect of this approach was the design of a repository concept for the two known potential host rock formations; huge Jurassic claystone layers in the northern part of Germany and thinner but well-known claystone layers in the South, also known as Opalinus Clay. For the northern reference geology, the disposal of unshielded canisters in vertical boreholes was designed as preferred emplacement concept. For the Opalinus Clay, drift disposal of shielded POLLUX® casks was identified as the most suitable emplacement concept. In addition, the ERNESTA study (Development of Technical Concepts for the Retrieval of Waste Containers with Heat-generating Waste and Spent Fuel from Repositories in Salt and Clay Formations) was initiated to investigate in parallel how to fulfil the requirement for retrievability in both concepts. In Germany, retrievability is a design criterion and requirement for licensing stipulated by the “Safety Requirements Governing the Final Disposal of Heat-Generating Radioactive Waste”, established in 2010.