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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Wyoming as a hub for new nuclear manufacturing and microreactor deployment?
A 60-year-old Wyoming industrial machinery company is partnering with nuclear innovator BWX Technologies to deploy 50-megawatt microreactors in America’s heartland over the coming years to provide carbon-free heat and power for industrial users.
Masahiro Seki, Toshihiko Yamanishi, Wataru Shu, Masataka Nishi, Toshihisa Hatano, Masato Akiba, Hiroshi Takeuchi, Kazuyuki Nakamura, Masayoshi Sugimoto, Kiyoyuki Shiba, Shiro Jitsukawa, Etsuo Ishitsuka, Hiroshi Tsuji
Fusion Science and Technology | Volume 42 | Number 1 | July 2002 | Pages 50-61
Technical Paper | doi.org/10.13182/FST02-A212
Articles are hosted by Taylor and Francis Online.
An overview of the present status of development of fusion nuclear technologies at Japan Atomic Energy Research Institute is presented. A tritium handling system for the ITER was designed, and the technology for each component of this system was demonstrated successfully. An ultraviolet laser with a wavelength of 193 nm was found quite effective for removing tritium from in-vessel components of D-T fusion reactors. Blanket technologies have been developed for the test blanket module of the ITER and for advanced blankets for DEMO reactors. This blanket is composed of ceramic Li2TiO3 breeder pebbles and neutron multiplier beryllium pebbles, whose diameter ranges from 0.2 to 2 mm, contained in a box structure made of a reduced-activation ferritic steel, F82H. Mechanical properties of F82H under a thermal neutron irradiation at up to 50 displacements per atom (dpa) were obtained in a temperature range from 200 to 500°C. Design of the International Fusion Materials Irradiation Facility (IFMIF) has been developed to obtain engineering data for candidate materials for DEMO reactors under a simulated fusion neutron irradiation up to 100 to 200 dpa, and basic development of the key technologies to construct the IFMIF is now under way as an International Energy Agency international collaboration.