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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.
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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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Suk-Kwon Kim, Bong Guen Hong, Dong Won Lee, Do Heon Kim, Young-Ouk Lee
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 746-750
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8998
Articles are hosted by Taylor and Francis Online.
A system analysis has been performed to develop the concepts for a fusion reactor and to identify the design parameters by using the tokamak system analysis code at KAERI (Korea Atomic Energy Research Institute). The system code elucidates the device parameters which satisfy the plasma physics and engineering constraints by taking into account a wide range of plasma physics and technology effects, simultaneously. The calculation of 1-D neutronic system code was coupled with this tokamak system code to optimize the reactor parameters. The numerical simulation for blanket neutronics was performed with MCNP5 code to calculate the tritium breeding ratios and neutron multiplications, which were the input parameter of system code. With the coupled system analysis and one-dimensional neutronic calculation, we assessed various types of DEMO blanket concepts with the requirements for the DEMO selected as to demonstrate the tritium self-sufficiency, to generate a net electricity amount, and for a steady-state operation.