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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.
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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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Masahiro Seki, I. Yamamoto, A. Sagara
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 300-307
Technical Paper | Fusion Energy - Fusion Plenary and Overview | doi.org/10.13182/FST05-A709
Articles are hosted by Taylor and Francis Online.
After the ITER/EDA study, Japanese activities in fusion technology have been mainly devoted to DEMO reactors. The paper intends to overview these activities.With respect to the test blanket modules, solid breeder blankets with ferritic steel structure cooled by helium and water are being developed by JAERI in cooperation with universities and NIFS. Advanced blankets are being developed by universities and NIFS. In the area of tritium processing technology, R&D has been focused on the blanket tritium recovery technology. In terms of the superconducting magnet, JAERI has performed basic research for the Fusion Power Demonstration Plant, aiming at realization of toroidal filed higher than 13 T using innovative superconductors, such as Nb3Al and High Temperature Superconductors (HTS). In the R&D of negative ion based NBI technologies, a H- beam of 110 mA has been stably accelerated up to 0.9 MeV, which corresponds to the current density of 80 A/m2. A beam power of 13.1 MW at 180 keV has been injected from three injectors in the LHD N-NBI. With respect to the radio-frequency heating technology, development of 170GHz ITER gyrotron has been progressed to achieve a 500kW for 100 sec operation in JAERI. Long pulse injection for 766 sec with 72 kW at 84 GHz was achieved in a LHD ECH experiment.