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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
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.