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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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Fusion Science and Technology
Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Joel Weisman, Shahab Ileslamlou
Fusion Science and Technology | Volume 13 | Number 4 | May 1988 | Pages 654-659
Technical Paper | Blanket Engineering | doi.org/10.13182/FST88-A25140
Articles are hosted by Taylor and Francis Online.
The theory previously developed for slightly subcooled and low-quality critical heat flux (CHF) has been extended to highly subcooled conditions. The revised model is shown to predict CHF values under these conditions for water, nitrogen, and refrigerant 113. This new approach should allow optimal design of subcooled boiling systems for cooling of fusion reactor components subjected to very high heat fluxes.
