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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.
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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Hungyuan B. Liu, Robert M. Brugger
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 151-156
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35026
Articles are hosted by Taylor and Francis Online.
Convenient, economical epithermal neutron beams will be needed in the future for boron neutron capture therapy (BNCT). We studied two concepts for producing epithermal neutron beams with low-power reactors. The first design is a 100-kW reactor with a 235U fission plate placed outside the reflector region, plus an Al/Al2O3 moderator assembly. The beam, which is directed forward, delivers a flux of epithermal neutrons of 0.8 × 109 n/cm2·s and a fast neutron dose of 4.4 × 10−11 cGy·cm2/nepi. The second design is based on a slab reactor plus a similar Al/Al2O3 moderator assembly. With an operating power of 50 kW, the beam has an intensity of 1.4 × 109 n/cm2.s and a fast neutron dose of 4.6 × 10−11 cGy·cm2/nepi; this beam also is directed forward. These epithermal neutron beams should be acceptable for BNCT; a treatment could be completed in ∼1 h, and the fast neutron dose to the skin would not be the limiting dose. Such small reactors should be practicable in a hospital location.
