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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jun 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
Hinkley Point C gets over $6 billion in financing from Apollo
U.S.-based private capital group Apollo Global has committed £4.5 billion ($6.13 billion) in financing to EDF Energy, primarily to support the U.K.’s Hinkley Point C station. The move addresses funding needs left unmet since China General Nuclear Power Corporation—which originally planned to pay for one-third of the project—exited in 2023 amid U.K. government efforts to reduce Chinese involvement.
Yusuke Ohashi, Masamitsu Shimaike, Takashi Matsumoto, Nobuo Takahashi, Kaoru Yokoyama, Yasuyuki Morimoto
Nuclear Technology | Volume 209 | Number 5 | May 2023 | Pages 777-786
Technical Note | doi.org/10.1080/00295450.2022.2145136
Articles are hosted by Taylor and Francis Online.
At the Ningyo-Toge Environmental Engineering Center, technical developments related to uranium refining conversion and enrichment have been completed and decommissioning of these facilities has begun. The error between the quantity of dismantled materials estimated from the facility design drawings and the actual quantity of the dismantled materials was about 1.7% when averaged over the entire facilities already dismantled. Most of the dismantled materials, which have no contamination history and were properly managed, were confirmed to have surface radioactivity concentrations below the detection limit and could be carried out to recyclers as nonradioactive (NR) waste. The dismantled materials that could not be certified as NR needed to be cleared and reused. By evaluating two types of gamma rays of 234mPa from the mockup dismantled objects, it was found that uranium corresponding to a clearance level (1.2 × 102 Bq/kg) could be quantified.