ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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
Corporate powerhouses join pledge to triple nuclear energy by 2050
Following in the steps of an international push to expand nuclear power capacity, a group of powerhouse corporations signed and announced a pledge today to support the goal of at least tripling global nuclear capacity by 2050.
R. V. Arutyunyan, D. A. Pripachkin, K. S. Dolganov, S. V. Tsaun, S. N. Krasnoperov, D. V. Aron, D. Yu. Tomashchik, E. L. Serebryakov, S. V. Panchenko, A. V. Shikin
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 92-100
Technical Paper | doi.org/10.1080/00295450.2018.1432839
Articles are hosted by Taylor and Francis Online.
Specialized computer codes that model the behavior of aerosol particles propagating through a system of pipes or air ducts are used for assessment of aerosol particle deposition. Developed in Russia, SOCRAT/V3 is one such code. SOCRAT/V3 was used for modeling of the transport of radioactive aerosols containing the 137Cs radionuclide through an air duct during a real emergency. The obtained results of the modeling were used to estimate the exposure dose rate (EDR) of gamma radiation near the air duct. The results of the estimation were compared with data of real measurements of the gamma-radiation EDR along the air duct.
This paper proposes an approach to assessment of source term in the case of radioactive aerosol releases using (1) a thermophysical code (SOCRAT/V3), allowing modeling of physical processes that influence the formation and transport of aerosols, and (2) data of in situ measurements for the external EDR from contaminated air ducts.
