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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
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.