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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
T. Hayashi, T. Suzuki, M. Yamada, M. Nishi
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 510-514
Fueling and Tritium Handling Technology (Poster Session) | doi.org/10.13182/FST98-A11963663
Articles are hosted by Taylor and Francis Online.
The accountancy of tritium stored in the Zirconium-Cobalt (ZrCo) bed with 25 g of tritium storage capacity has been investigated by “in-bed” gas flowing calorimetric method for a few years. This type of calorimetry uses the temperature raise of helium (He) gas circulated through a secondary coil line installed in the ZrCo tritide. Recently, the basic calorimetric characteristics was demonstrated well within 1 % accuracy of the ITER requirement using 22 g of tritium under actual storage system conditions, such as hydrogenation-dehydrogenation of tritium, long-term storage (3He accumulation inside of tritide vessel), and DT mixture storage. Based on the experimental data, a 100 g of tritium storage bed (ITER size) was designed and its calorimetric performance was discussed.