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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.”
José M. Balmisa, Micah D. Lowenthal, Ehud Greenspan, Javier Sanz, Nathan Stone
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 964-968
Neutronics Experiments and Analysis (Poster Session) | doi.org/10.13182/FST98-A11963737
Articles are hosted by Taylor and Francis Online.
A new practical method has been developed for calculating neutron-activation inventories of target material in inertial fusion energy (IFE) reactors such as HYLIFE-II. It accounts for irradiation both in the target and in the internal blanket and for material circulation in and out of the primary loop. The continuous removal of target material in the real system is approximated by a batch extraction (BE). A single target is followed through its lifetime in the reactor using “transition matrices” for activation and decay which are generated by the ACAB code package. The inventory of all the isotopes of interest accumulating in the reactor is obtained by superimposing the contribution of single targets. The new BE model simulates, within minutes, the evolution of more than 150 isotopes over the 30-year reactor lifetime, explicitly accounting for the millions of neutron pulses experienced by a single target and summing the inventories of all the targets.