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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
U.S. nuclear capacity factors: Ideal for data centers?
Baseload nuclear generation doesn’t get the respect it deserves, if you ask nuclear operators. But the hyperscale data centers that process our digital lives—like the one right next to the Susquehanna plant in northeastern Pennsylvania—are pushing electricity demand up. Clean, reliable capacity now looks a lot more valuable.
Yoshihiro Hirao, Koichi Okuno, Ken-ichi Kimura, Mikihiro Nakata, Tomohiro Ogata, Yukio Sakamoto, Ken-ichi Tanaka, Koji Oishi, Satoshi Ishikawa, Masahiro Yoshida, Toshio Amano, Kazuaki Kosako, Toshinobu Maenaka
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 185-192
Research Article | doi.org/10.1080/00295639.2023.2177077
Articles are hosted by Taylor and Francis Online.
The working group on shielding materials under the Standards Committee of the Atomic Energy Society of Japan has been studying the standard composition of shielding concrete that has a clear basis for use in the design of Japanese facilities. The policy for determining the composition, the procedure of study, the results obtained to date, and future tasks are described. Concrete is broadly classified into silicon type and calcium type depending on the aggregate. The reference mix design and composition were selected from the Japanese recommendation, and minor elements in the composition were replaced with silicon and calcium while preserving their weight in order to reduce regional differences. However, the penetration dose calculation for 235U thermal fission neutrons indicated that iron and carbon should be retained. The penetration dose calculations for photons from 235U prompt fission and radioisotopes showed that the attenuation ratios of silicon-type and calcium-type concretes differ in the energy region where electron pair production becomes dominant. The water content of concrete was found to vary with thickness as a result of moisture migration analysis over time. Finally, a draft composition of silicon-type concrete by thickness was determined using the residual water content at 60 years after placement. A method for correcting the elemental content under different mix conditions was also proposed.