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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.
Yasuhisa Oya, Takuji Oda, Satoru Tanaka, Kenji Okuno
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1423-1426
Detritiation and Isotope Separation | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12698
Articles are hosted by Taylor and Francis Online.
The tritium recovery technique at the steam generator in fast breeder reactor under the double pipe concept was studied by both of experiment and simulation. The permeation of tritium was lowered at ~1000ppm oxygen in Ar as a recovery gas. But tritium is easily converted to water form by adding 10ppm oxygen. To explain these experimental results and expand the tritium behavior at double pipe concept, DFT and Monte Carlo simulations were applied. The surface oxide layer mode was developed and stability of tritium was evaluated. It was found that most stable structure was formed in the oxide layer although tritium is unstable at the surface of oxide layer. Tritium permeation rate was almost the same even if the oxide layer was formed, but the tritium retention is enhanced by adding the oxide layer. To expand these results to tritium permeation and recovery model, numerical analysis was performed as a function of sweep rate, material thickness and thickness of surface oxide layer. It was found that control of sweep rate is one of key factors. But the design restriction, control of oxide layer thickness by flowing O2+Ar gas will be potential option for the recovery of tritium at steam generator.