ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
DOE issues final RFQ for WIPP clean energy initiative
The Department of Energy’s Office of Environmental Management has issued a request for qualifications for interested parties and prospective offerors looking to enter into a realty agreement for carbon-pollution-free electricity (CFE) projects at the department’s Waste Isolation Pilot Plant site in southeastern New Mexico.
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.