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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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November 2024
Latest News
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
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.