ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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
BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
Jiyang Yu, Baoshan Jia
Nuclear Science and Engineering | Volume 142 | Number 2 | October 2002 | Pages 230-236
Technical Paper | doi.org/10.13182/NSE02-A2303
Articles are hosted by Taylor and Francis Online.
The algorithm for the transient containment analysis code (PCCSAC) developed to analyze the AC600 passive containment cooling system (PCCS) is described. The AC600 reactor uses passive external spray from an elevated tank. The PCCSAC code has been developed with a number of unique modeling capabilities for the AC600 PCCS. The unique feature of the PCCSAC code is the nine-equation model that classifies the fluid in the containment as steam, noncondensable air, and liquid water. The model includes the k- turbulence model and a diffusion model for gas flow. The code considers nonuniform spatial factors. It can analyze most physical phenomena in the AC600 PCCS. The code was validated by comparing the present results with those of the COMMIX code for the analysis of a postulated small-scale model of AP600. The PCCS response of AC600 during design-basis accidents is analyzed.