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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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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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Il S. Lee, Kune Y. Suh
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 265-281
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3761
Articles are hosted by Taylor and Francis Online.
A liquid-metal-cooled fast reactor Proliferation-resistant Environment-friendly Accident-tolerant Continuable-energy Economical Reactor (PEACER) is being developed at Seoul National University with metallic-type U-Pu-Th fuel and lead-bismuth (Pb-Bi) coolant, employing the steam-generating Rankine cycle without an intermediate loop. The natural circulation potential is a key ingredient of the liquid-metal reactor design. PEACER is designed as a loop system, which increases the natural circulation capacity and reduces the maintenance cost. This work is concerned with design of a large-scale test loop Heavy Eutectic Loop Integrated Operation System (HELIOS) to simulate thermal-hydraulic behavior of Pb-Bi in the PEACER system following a single-phase one-dimensional flow loop model. The full-height loop is being constructed for Pb-Bi natural-circulation testing and operating procedure development. Electrically heated rods are used in the heating section, and a water-cooling method is adopted in the cooling section. HELIOS has the same elevation difference between thermal centers of the heat source and heat sink but reduced piping diameters.