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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.
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2021 Student Conference
April 8–10, 2021
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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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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.
R. M. Hunt, M. Narula, M. A. Ulrickson, T. T. Martin, A. Ying
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 38-42
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | dx.doi.org/10.13182/FST09-A8872
Articles are hosted by Taylor and Francis Online.
Understanding the manner in which the First Wall Qualification Mockup (FWQM) responds structurally to simulated ITER conditions is important to the establishment of a reliable first wall. This paper provides a thermal and structural response analysis for the first round of qualification tests performed at Sandia National Laboratories. The results display the stresses and strains created in the FWQM as a result of the thermal expansion that occurred when subjected to cyclic heat flux under simulated ITER normal and MARFE conditions. From this structural response, further insight may be gained into the likelihood of fatigue failure of the Beryllium//CuCrZr interface once the first wall is in operation in ITER. While fully determining the reliability of this joint is beyond the scope of this study, some suggestions are made as to how this topic might be addressed with further research. Also investigated are the thermal patterns seen during testing that indicated slight variation from the intended test parameters. It is shown that these disparities from the ideal test parameters do not significantly affect the qualification of the FWQM.
