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Division Spotlight
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.
Meeting Spotlight
2021 Student Conference
April 8–10, 2021
Virtual Meeting
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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Nuclear Science and Engineering
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Fusion Science and Technology
January 2021
Latest News
Fukiushima Daiichi: 10 years on
The Fukushima Daiichi site before the accident. All images are provided courtesy of TEPCO unless noted otherwise.
It was a rather normal day back on March 11, 2011, at the Fukushima Daiichi nuclear plant before 2:45 p.m. That was the time when the Great Tohoku Earthquake struck, followed by a massive tsunami that caused three reactor meltdowns and forever changed the nuclear power industry in Japan and worldwide. Now, 10 years later, much has been learned and done to improve nuclear safety, and despite many challenges, significant progress is being made to decontaminate and defuel the extensively damaged Fukushima Daiichi reactor site. This is a summary of what happened, progress to date, current situation, and the outlook for the future there.
P. W. Humrickhouse, J. P. Sharpe, M. L. Corradini
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 1022-1026
Technical Paper | Tritium, Safety, and Environment | dx.doi.org/10.13182/FST07-A1629
Articles are hosted by Taylor and Francis Online.
The Toroidal Dust Mobilization eXperiment (TDMX) has been developed to investigate the mobilization of dust in fusion reactor Loss of Vacuum Accident (LOVA) scenarios. TDMX data will be utilized to validate new computational models for dust resuspension and transport in LOVAs. This work describes the modeling of the compressible vessel filling in TDMX using the CFD code Fluent. Results for fast (~0.1 s) pressure transients are found to agree well with experimental and analytical results. Modeling longer transients has thus far been less successful, due primarily to the difficulty in resolving the accompanying small flow passages.
