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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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February 2025
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Latest News
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
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.