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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Xiaohua Cao, Wende Shen, Jingping Wan, Huajin Tan, Yixiang Jiang, Benfu Yang
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 550-555
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30460
Articles are hosted by Taylor and Francis Online.
The first Chinese in-situ tritium release experiment is being carried out in the fission reactor SPRR-300 in the Southwest Institute of Nuclear Physics and Chemistry (SWINPC). Several runs of the experiment were conducted to study tritium generation and release behaviors from China-made γ-LiAlO2 pellets. The effects of some key operational factors (temperature, sweep gas composition and flow rate) upon tritium release were studied. The results show that the equilibrium tritium release rate at different temperatures approached the tritium generation rate obtained from neutron calculations. The tritium concentration in the sweep gas decreased with increasing the flow rate. Addition of a small quantity of hydrogen greatly enhanced the release of tritium. It was also found that the tritium released in the sweep gas was mostly in the form of HT. However, when the generated tritium was not purged in time, the HTO fraction increased gradually. By using the inventory difference method, through the special run which lasted 72 hours, we determined the diffusion coefficient for tritium in γ-LiAlO2. The obtained diffusivity and its activation energy were compared with those from other experiments. It was found that the value of Q was close to those from LILA and TTTEx experiments, but the value of D0 was smaller.
