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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
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.