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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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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
PG&E to dredge Diablo Canyon intake system
The owners of the Diablo Canyon nuclear power plant plan to dredge a massive buildup of shoaled sediment from its seawater intake cove.
Pacific Gas and Electric spokesperson Suzanne Hosn said, “The dredging project in the Diablo Canyon marina will remove approximately 70,000 cubic yards of sediment to prevent circumstances that could impact the power plant’s cooling system. Dredging will take place for the first time since operations began because of a rapid increase in sediment.”
A C Bell, J Williams, J D Neilson, A Perevezentsev
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 626-631
Device, Facility, and Operation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST41-626
Articles are hosted by Taylor and Francis Online.
Around 100 grams of tritium was supplied to the JET machine during the 1997 DTE1 campaign. A significant proportion of this was retained in the machine and only released slowly over the succeeding operational and maintenance campaigns Tritium is also present though permeation and surface adsorption of materials. Means of detritiation of JET waste which could be applied within the facility are being developed. These must take into account the full waste cycle including the generation of secondary waste and the possibility of recovery for re-use of tritium. Each of the typical JET tritiated waste streams is described and the detritiation processes being developed and under consideration are discussed.