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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
“The time is now” to advance U.S. nuclear—Part 1
The Nuclear Regulatory Commission is gearing up to tackle an influx of licensing requests and oversight of advanced nuclear reactor technology, especially small modular reactors.
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.
