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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.
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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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Fusion Science and Technology
Latest News
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Takuya Nagasaka, Takeo Muroga, Akio Sagara, Hiroshi Yukawa, Tomonori Nambu
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1580-1583
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12736
Articles are hosted by Taylor and Francis Online.
Tensile and creep strength of pure V, Nb, Ta, and Nb-9W alloy were examined at 600 °C to assess their applicability as hydrogen permeation material for the recovery of tritium from the high temperature liquid breeder blanket of a fusion reactor. The Nb-9W alloy required a comparatively higher annealing temperature to achieve good ductility. Based on tensile strength results, it is estimated that a permeation wall thickness of 0.1 mm is achievable. According to creep rate of Nb-9W alloy, design stress maybe decreased below 1/3 of yield stress.