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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Soon K. Lee, Maolong Liu, Edward D. Blandford, Youho Lee (Univ of New Mexico), Nicholas R. Brown (Penn State), Hang Ban (Univ of Pittsburgh), Colby B. Jensen (INL), Kurt A. Terrani (ORNL)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 414-427
This study presents an investigation of critical heat flux (CHF) variation upon the use of candidate Accident Tolerant Fuel (ATF) cladding (FeCrAl alloy) compared to Inconel600, Zircaloy-4 and the 2006 CHF look-up table by conducting the flow boiling experiments under steady-state condition at an atmospheric pressure and at fixed inlet temperatures and a mass flux. To directly compare the CHF change during transient condition relevant to Reactivity Initiated Accident (RIA), experiments were done at the same thermodynamic quality and flow condition following the steady-state condition CHF results. An increased thermal safety margin of FeCrAl alloy compared to other tested alloys were identified as well as a disagreement between the Zircaloy-4 experimental CHF results and the 2006 CHF look-up table, which implies limitation of the current thermal-hydraulic codes for interpreting fuel design safety margin. To gain a better understanding on the implications of wettability on CHF, contact angle measurements were carried out on both fresh and oxide surfaces and the detailed morphology analysis was done by scanning electron microscope, which suggests a negligible impact of the wettability on the flow boiling CHF.