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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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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.
Gyoo Won Suh and Hee Cheon No
Nuclear Science and Engineering | Volume 90 | Number 3 | July 1985 | Pages 236-247
Technical Paper | doi.org/10.13182/NSE85-A17765
Articles are hosted by Taylor and Francis Online.
The USODA (U-tube Steam Generator Controller Design Analysis) code was developed to simulate the transient behavior of a vertical natural circulation U-tube steam generator in pressurized water reactors and to design the optimal level controller. The steam generator was represented by sixth order linear differential equations through matrix reduction. The momentum equation for the recirculation flow models the effects of the separators, U-bend regions, and spatial acceleration. To assure stability, the Lyapunov theorem was adopted. The optimal gains were obtained by minimizing the quadratic performance index and by using both Newton-Raphson and successive overrelaxation methods, which guarantee fast convergence. Sample calculations for Korea Nuclear Unit 2 showed that a control system consisting of standard proportional integral differential controls can be successfully employed for the control of water level. The optimization procedure led to a stable system with good controlled response.