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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Fusion Science and Technology
Latest News
DOE opens pilot program to authorize test reactors outside national labs
Details of the plan to test new reactor concepts under the Department of Energy’s authority but outside national laboratory boundaries—first outlined in one of the four executive orders on nuclear energy released on May 23—were just released in a request for applications issued by the DOE.
M. Matsuyama, K. Shinmura, Z. Chen, Y. Torikai
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1491-1494
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12714
Articles are hosted by Taylor and Francis Online.
Solubility of tritium in Cu-Be(2 mass%) alloy was determined by means of measurement of a tritium depth profile in the alloy. Tritium exposure to the samples was conducted under the following conditions: pressure, 0.4 to 2.6 kPa; temperature, 350 to 450°C; exposure time, 4 to 11 hours. Tritium depth profiles were obtained by chemical etching after the exposure. Remarkably high tritium concentration appeared in surface layers within 0.5 m, whereas almost constant concentration was observed from 10 m to the bulk. It was found, therefore, that surface tritium should be omitted in evaluation of the solubility of tritium. In addition, it was seen that dissolution of tritium into Cu-Be alloy obeys the Sieverts' law from the pressure dependence, and the solubility of tritium in Cu-Be alloy was lower than that in pure copper. From the temperature dependence of solubility, the heat of solution of tritium was determined as 17 kJ/mol.
