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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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June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Excelsior University student section awarded community education grant
The American Nuclear Society Student Section at Excelsior University in Albany, N.Y., was awarded a $5,000 grant from the ANS Student Section Strategic Fund initiative for its program, Empowering Tomorrow’s Nuclear Innovators: A Collaborative Approach to Nuclear Technology Education and Awareness.
Sadao Uchikawa, Tsutomu Okubo, Yoshihiro Nakano
Nuclear Technology | Volume 172 | Number 2 | November 2010 | Pages 132-142
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10900
Articles are hosted by Taylor and Francis Online.
The FLWR is a boiling water reactor type with a core consisting of hexagonal-shaped fuel assemblies with a triangular-lattice fuel rod configuration, which has been proposed in order to ensure a sustainable energy supply in the future based on well-established light water reactor technologies. This paper proposes a new concept of fuel assembly design named FLWR/MIX. The first stage of FLWR is designed to conserve plutonium effectively with a fissile plutonium conversion ratio of around 1.0, keeping negative void reactivity characteristics. Enriched UO2 fuel rods are arranged in the peripheral region of the assembly, surrounding the mixed oxide (MOX) fuel rods in the central region. Performance evaluation shows that the FLWR/MIX concept is effective for controlling the void reactivity characteristics in the tight-lattice fuel rod configuration and is promising under the framework of the UO2 and MOX fuel technologies and related infrastructures that have been established for the current LWR-MOX utilization.