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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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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Fusion Science and Technology
Latest News
Take steps on SNF and HLW disposal
Matt Bowen
With a new administration and Congress, it is time once again to ponder what will happen—if anything—on U.S. spent nuclear fuel and high-level waste management policy over the next few years. One element of the forthcoming discussion seems clear: The executive and legislative branches are eager to talk about recycling commercial SNF. Whatever the merits of doing so, it does not obviate the need for one or more facilities for disposal of remaining long-lived radionuclides. For that reason, making progress on U.S. disposal capabilities remains urgent, lest the associated radionuclide inventories simply be left for future generations to deal with.
In March, Rick Perry, who was secretary of energy during President Trump’s first administration, observed that during his tenure at the Department of Energy it became clear to him that any plan to move SNF “required some practical consent of the receiving state and local community.”1
Hisashi Sagawa, Kuniaki Miura, Hiroshi Kawamura, Rokuro Oyamada
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1073-1077
Analysis and Accountancy | 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-A30549
Articles are hosted by Taylor and Francis Online.
To obtain engineering data for a design of a fusion blanket, a program in which a mock-up simulating a blanket structure is irradiated is proceeded in the JMTR (Japan Materials Tasting Reactor) project.1 It is indispensable for this irradiation test to purge the tritium produced in the mock-up by the sweep gas and to measure the tritium concentration in the sweep gas on line. However, the bad effects such as tritium adsorption on the inner surface of the pipe and tritium diffusion from the pipe are apprehended, because the distance between the mock-up and an ionization chamber is about 20m long. Therefore, it is necessary to develop a sweep gas sensor which can measure the tritium concentration in the mock-up directly without the above apprehension. A sweep gas sensor had been fabricated on trial and several performance tests were carried out. From the results of the tests, it was found that this sensor could be used at the atmosphere of high temperature of 600–700°C and had good response.
