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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
H. Ueda et al.
Fusion Science and Technology | Volume 63 | Number 1 | May 2013 | Pages 316-318
doi.org/10.13182/FST13-A16940
Articles are hosted by Taylor and Francis Online.
This paper describes the initial result of simulation study of neutron production by NBI heating in the GAMMA 10 tandem mirror by using a buildup numerical simulation code. In the GAMMA 10 central-cell, high energy ions have localized in the neutral beam injection port and the other bounce point due to the perpendicular injection. By considering this mechanism, the position of the test zone for neutron irradiation is assumed and the amount of the neutron flux is evaluated. The neutron flux is about 1.3 kW/m2, for high-density mode and about 1.2 kW/m2, for hot-ion mode.
