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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
DOE’s Wright appears before House subcommittee
Wright
Secretary of Energy Chris Wright testified before a hearing of the U.S. House of Representatives Committee on Appropriations, Subcommittee on Energy and Water Development and Related Agencies, on May 7, to answer questions about the DOE budget and priories for fiscal year 2026.
Wright’s testimony: Wright said that the DOE was taking steps to accelerate innovation in commercial nuclear development. “In the past 100 days, DOE has issued two disbursements to support the reopening of Michigan’s Palisades nuclear energy plant. We allocated high-assay low-enriched uranium material to five U.S. advanced nuclear reactor developers to boost domestic reactor deployment.”
He added that it was imperative for the nation to strengthen its nuclear future and that he would take immediate action to accelerate the deployment of small modular reactors.
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.
