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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Y. Torikai et al.
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1057-1060
Contamination and Waste | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12598
Articles are hosted by Taylor and Francis Online.
A batch process concept for the decontamination from tritium of fusion reactor materials based on a hydrothermal treatment is under development at HRC. Essentially, tritium-loaded material is heated in a tightly closed vessel containing a defined amount of water. The objective of the water is to “capture” the released tritium in a small volume of liquid. For the detritiation, stainless steel temperatures in the range 393-473 K over a period of several days were found to be adequate. From the results it appears that by and large the released tritium accumulates in the purposely introduced water. The achieved degree of decontamination was estimated from the tritium concentration in the water and the tritium that remained in the decontaminated material. Tritium trapped in the surface layer of stainless steel was not reduced by the isochoric hydrothermal treatment in the same proportion as that in the bulk.