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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
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis 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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Nuclear Science and Engineering
June 2023
Nuclear Technology
Fusion Science and Technology
July 2023
Latest News
NRC advisors give nod to Hermes construction permit
Having completed its review of the construction permit application for Kairos Power’s Hermes test reactor early last month, the Nuclear Regulatory Commission’s Advisory Committee on Reactor Safeguards (ACRS) recently submitted its conclusions to the agency, recommending approval.
Won-Jin Cho, Changsoo Lee, Geon Young Kim
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 225-240
Technical Paper | doi.org/10.1080/00295450.2017.1369804
Articles are hosted by Taylor and Francis Online.
For a spent fuel repository, the possible application of the concepts of a multilayer repository with a two- or three-story disposal tunnel and a multicanister repository in which two or three canisters are emplaced in a deposition hole is assessed from the viewpoint of temperature, mechanical stability, and nuclear criticality. The results show that the concepts of multilayer and multicanister repositories are applicable to the geological repository without deterioration of the mechanical stability and nuclear criticality safety. Their adoption in the spent fuel repository can improve the disposal density up to 200% to 400% depending on the applied peak temperature limit under the given thermal constraint and site conditions.