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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
S. C. McCool, P. H. Edmonds, G. G. Castle
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 114-128
Technical Paper | Fusion Fuel Cycle | doi.org/10.13182/FST92-A29731
Articles are hosted by Taylor and Francis Online.
The use of 6LiT pellet injection for the Burning Plasma Experiment (BPX), the International Thermonuclear Experimental Reactor (ITER), or reactor fueling using the low ion temperature catalyzed reaction 6LiT + D-D proposed by Krasnopol'skij et al. is investigated. Solid LiT has significant advantages as a pellet material over cryogenic deuterium-tritium because of its higher heat of sublimation, mechanical strength, attainable pellet velocity, and plasma penetration. The implications of this for ignition scenarios are discussed. Injection of LiT has the additional advantage of inherent lithium wall conditioning, which has been shown in the Tokamak Fusion Test Reactor (TFTR) and the Texas Experimental Tokamak (TEXT) to have effects similar to boronization. The injection of LiH pellets has been demonstrated in TEXT, and observed pellet penetration is compared with an ablation model, which is then used to predict LiT penetration in ITER and BPX.