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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Latest News
Is waste really waste?
Tim Tinsley
I’ve been reflecting on the recent American Nuclear Society Winter Conference and Expo, where I enjoyed the discussion on recycling used nuclear fuel to recover valuable minerals or products for future applications. I have spent more than 30 years focusing on dissolving and separating nuclear material, so it was refreshing to hear the case for new applications being made. However, I feel that these discussions could go further still.
Radiation is energy, something that our society seems to have an endless need for. A nuclear power station produces a lot of radiation that is mostly discarded. But once fuel has been used, it still produces significant levels of radiation and heat energy. The associated storage, processing, and eventual disposal of this used fuel requires careful management and investment to protect systems and people from the radiation. Should we really disregard—and discard—this energy source, along with all the valuable minerals in the used fuel, when we could instead use it to deliver significant value to society?
Sang Ji Kim, Pham Nhu Viet Ha, Jae Yong Lim, Won Sik Yang
Nuclear Technology | Volume 186 | Number 3 | June 2014 | Pages 390-402
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-90
Articles are hosted by Taylor and Francis Online.
A core design study to convert a breakeven core into a transuranic (TRU) burner is performed for a 600-MW(electric)–rated metal-fueled sodium-cooled fast reactor. No change in the core and subassembly layouts is assumed, which only allows geometry variations within the fuel rods. Investigated alternatives are to use variable cladding thicknesses (VCTs), smearing fraction (SF) adjustments, and annular fuel rod concepts with a central liner of a variable diameter consisting of void, Zr, B4C, Al, etc. The VCT concept could not be employed due to a too-high clad inner wall temperature. A SF adjustment below a typical fraction of 75% leads to moderate TRU burning and a reduced sodium void worth but also to a relatively high burnup swing. Placing a central nonfuel rod with the fuel arranged in an annular ring affects the core performance and reactivity coefficients, depending on whether it is a moderator or an absorber. In general, candidate materials of high atomic numbers contribute to large positive sodium void worths but also enhanced negative expansion effects. Among the light elements, vanadium reveals a favorable performance with comparable TRU burning and a reduced sodium void worth, suggesting this material can be regarded as a substitute for sodium in the solid state.