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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
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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February 2024
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.
Yu-ya Furukubo, Ken-ichi Fukuda, Masabumi Nishikawa, Sergey Beloglazov
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 658-661
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A1011
Articles are hosted by Taylor and Francis Online.
It is required to develop an efficient tritium fueling cycle keeping the overall tritium breeding ratio larger than 1.0 and a reliable tritium confinement system assuring the radiation safety of tritium in construction of the D-T fusion reactor. The blanket is the place where the tritium recovery system has contact with the cooling system for electricity generation at the elevated temperature. Therefore, design of efficient means to recover bred tritium with minimum permeation loss is to be made.It is proposed in this study to construct a recovery system using the Pd alloy with adsorption bed after a precious metal catalyst bed. Effects of existence of water on dissociation reaction of hydrogen on palladium alloy membrane and on recombination reaction are discussed in this study for the case when 800 Pa of water vapor is introduced to the permeation primary side and/or permeation secondary side for the case when water vapor co-existed, and it was observed that water vapor prevents hydrogen permeation through palladium alloy at the lower temperature than 473K.