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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.