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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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Latest News
State legislation: Colorado redefines nuclear as “clean energy resource”
Colorado Gov. Jared Polis signed a bill into law on Monday that adds nuclear to the state’s clean energy portfolio—making nuclear power eligible for new sources of project financing at the state, county, and city levels.
Takeo Nishitani, Kenji Tobita, Kunihiko Okano, Masayushi Sugimoto, Toshihiko Yamanishi, Roland Heidinger, Angel Ibarra, Noriyoshi Nakajima
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 1-8
Technical Paper | doi.org/10.13182/FST13-733
Articles are hosted by Taylor and Francis Online.
In the Broader Approach (BA) activities, cooperated work on the DEMO design is undertaken with the IFERC project team and home teams in the EU and Japan. System code benchmarking to establish the common design tools and the definition of critical design issues have been progressed so far. The BA DEMO design work is focusing on the common critical issues such as divertor design, remote maintenance scheme, and blanket design. In parallel, safety research for the fusion power plant started re-analyses, which include severe events such as total loss of coolant without any electric power. In the DEMO R&D activities, five R&D tasks related to blanket materials and technology are carried out intensively according to the common interests of the EU and Japan for DEMO. A neutron source using the IFMIF/EVEDA prototype accelerator and the IFMIF/EVEDA lithium target test loop is under discussion as one of the major activities after 2017.