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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Hitesh Rajput, Tanmoy Som, Soumitra Kar
Nuclear Technology | Volume 192 | Number 2 | November 2015 | Pages 125-132
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-154
Articles are hosted by Taylor and Francis Online.
Fuel used in nuclear reactors contains fissile material. The fission process releases a huge amount of energy, and hence, the fissioning components must be held in a robust form capable of enduring high operating temperatures and an intense radiation environment. The shape and integrity of the fuel structures must be maintained over a period of several years within the reactor core to prevent the leakage of fission products into the reactor coolant. Further, the fuel rods must be in a nondistorted state for proper alignment in the fuel assembly to ensure proper fuel bundle power distribution. Improper core power distribution can breach the safety and operational limits on fuel and channel powers. The strategy discussed includes the methodology to verify the fuel assembly using image processing techniques. The methodology uses the Radon transform and contains four phases: image reading, preprocessing, Radon transform, and verification. The approach has been validated on 1026 fuel assemblies of a nuclear power plant, for which experimental results are shown.