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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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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.
E. Uspuras, A. Kaliatka
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 18-25
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3821
Articles are hosted by Taylor and Francis Online.
This paper evaluates the so-called weak heat conduction mechanism, i.e., the heat transfer from heated-up fuel channels in the radial direction to cooled channels through the adjacent graphite columns in the RBMK-1500 reactor. The influence of this mechanism on the calculation results for a long-term loss-of-coolant accident is investigated.Two possibilities for modeling the heat transfer in the radial direction, between adjacent graphite columns, using the system code RELAP5 are presented: (a) employing the interstructure heat conduction model built into the RELAP5-3D code and (b) employing the model of the reactor gas circuit, which supplies a mixture of gases into the reactor cavity.Both means allow one to predict the localized heatup in the RBMK core. However, the modeling of the reactor gas circuit in parallel with the reactor cooling circuit decreases the calculation time-step size quite significantly. The analysis results demonstrate the capability of the RELAP5-3D code to model heat conduction in the radial direction between different heat structures much more easily and a hundred times faster.