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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Jian Li, Aijing Shen, Jun Chen (SPIC/SNPTC)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1295-1305
Under the design basis accidents, steam release which is resulted from the rupture of reactor cooling system pipes or the rupture of main steam pipes will induce thermal and pressure impact on the containment, and that will probably destroy containment integrity. The passive containment cooling system (PCCS) can utilize natural force to remove heat and decrease pressure and temperature in the containment. So it can provide protection and cool down steel containment after accident. COSINE is a core and system integrated engine for nuclear power plant design and analysis. It is the first independent research and development nuclear power software in China. In this paper, COSINE containment code cosCont and GOTHIC are applied to evaluate the performance of PCCS of the advanced pressurized water reactor AP1000. Containment and concrete shielding are modeled, considering of steam condensation on the internal surface of the containment and air natural convection cooling on the external surface of the containment. The results show that pressure and temperature in the containment increase and environment side change little after high temperature and high pressure coolant sprayed into the containment. And the pressure in the containment did not exceed the safety design limit. Comparing the results of COSINE with GOTHIC, the calculation deviation of COSINE is within the acceptable range.