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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
May 2026
Latest News
Holtec hits milestones in Palisades restart, new reactor projects
Steam rises from the Palisades nuclear power plant. (Photo: Holtec International)
The restart of Palisades nuclear power plant in Covert, Mich., has hit a milestone with the passivation of its primary system, plant owner Holtec International announced Monday, even as a firm restart date has yet to be announced.
Passivation is a chemical process that improves corrosion resistance by making plant materials less reactive. During the process, the reactor’s primary system was brought to normal operating temperature and pressure. Holtec called this passivation phase an “essential step” in maintaining the long-term reliability of equipment.
Emilian L. Popov, Graydon L. Yoder, Valeri Velichkov
Nuclear Technology | Volume 149 | Number 3 | March 2005 | Pages 304-308
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3597
Articles are hosted by Taylor and Francis Online.
Detailed thermal-hydraulic analysis of commercial power reactors requires modeling of complex multidimensional thermal, fluids, and neutronic behavior. One code that has three-dimensional (3-D) thermal-hydraulic and neutronic capabilities is RELAP-3D. A comparison of RELAP-3D predictions to experimental data obtained during start-up of the Kozloduy VVER-1000 nuclear power plant in Bulgaria is presented here. The experiment has distinguishable 3-D hydraulics effects that allow for code model verification and reasonable agreement with the experimental results obtained.The transient investigated was conducted at 29% reactor power, and it was initiated from a steady state where three out of four reactor coolant pumps were operating. The transient consisted of the start-up of the nonoperating pump. Simulation results were compared to both temperature and pump data from the experiment. Temperature predictions compared reasonably well to the experimental data; however, discrepancies existed between predicted and experimental pump head values.