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
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
Oak Ridge Gaseous Diffusion Plant named a nuclear historic landmark
The American Nuclear Society recently announced the designation of three new nuclear historic landmarks: the Hot Fuel Examination Facility, the Neely Nuclear Research Center, and the Oak Ridge Gaseous Diffusion Plant K-25. Today’s article, the final offering in a three-part series, will focus on the historical significance of the Oak Ridge Gaseous Diffusion Plant K-25.
Rahim Nabbi, Wilfried Jahn, Gerhard Meister, Werner Rehm
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 172-189
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33216
Articles are hosted by Taylor and Francis Online.
Analysis of extreme water ingress accidents in the pebble bed high-temperature reactor of 500-MW(thermal) power during the first few minutes shows that the temperature coefficients of reactivity limit the power increase, presupposing no action of the shutdown system and other safety devices. The rupture of all steam generator tubes with the highest ingress rate of 55 kg/s results in a power maximum of 1.8 times the initial value after ∼1 min. The system pressure increases from the operating value of 40 bar up to the design value of 50 bar. Fuel temperatures do not reach values that cause fuel particle damage and fission product release. Hence, special requirements on the promptness of shutdown rod actions are not needed to limit accident consequences in the core. Overpressurization of the reactor vessel will arise, however, if water ingress with the highest rate continues. Water ingress at a small rate (7 kg/s), corresponding to the rupture of a few tubes, results in a rather slow power increase up to 1.3 times the initial value and to a primary system pressure of 43 bar after 5 min.