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
May 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
June 2026
Nuclear Technology
Fusion Science and Technology
Latest News
Savannah River marks the closure of another legacy waste tank
The Department of Energy’s Office of Environmental Management has received concurrence from regulators that Tank 14 at the Savannah River Site has reached preliminary cease waste removal (PCWR) status after radioactive liquid waste was successfully removed from the tank. PCWR is a regulatory milestone in the closure of SRS’s old-style waste tanks, which were built in the 1950s to store waste generated by the chemical separations of plutonium and uranium.
B. Hollrah, M. Bucknor, D. Lisowski, Y. Hassan, R. Vaghetto, R. Hu
Nuclear Technology | Volume 206 | Number 9 | September 2020 | Pages 1337-1350
Technical Paper | doi.org/10.1080/00295450.2020.1745039
Articles are hosted by Taylor and Francis Online.
Natural convection systems are a promising method to passively remove heat from reactor cavities during loss of forced flow accident scenarios. At Argonne National Laboratory (ANL), a highly instrumented Natural Convection Shutdown Heat Removal Test Facility (NSTF) was used to demonstrate the effectiveness of air-cooled natural convection systems. In previous work, RELAP5-3D simulations were performed on this facility with favorable comparisons to experiment for mass flow rate, pressure drop, air temperature increase, and air velocity. Both experimental and simulation efforts with this facility present a useful opportunity to perform a benchmark study with the System Analysis Module (SAM). SAM is an advanced thermal-hydraulic system code currently in development at ANL for advanced non–light water reactor safety analysis.