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
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Paul J. Babel, Barry H. Brosey, Carl H. Distenfeld
Nuclear Technology | Volume 87 | Number 2 | October 1989 | Pages 470-477
Technical Paper | TMI-2: Health Physics and Environmental Release / Nuclear Safety | doi.org/10.13182/NT89-A27739
Articles are hosted by Taylor and Francis Online.
The effort involved in determining the location and quantity of reactor fuel remaining in the nuclear auxiliary systems of the auxiliary/fuel handling building at Three Mile Island Unit 2 is discussed. The overall approach identifying the most likely locations for reactor fuel, the gamma-ray spectrometry system used, and the radiation transport computer codes and numerical analysis techniques used is also discussed. The results of the measurements show that a very small quantity of reactor fuel remains in the makeup and purification and the waste disposal liquid systems.
