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
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Robert J. Wolfgang, Rayford L. Patterson
Nuclear Technology | Volume 87 | Number 3 | November 1989 | Pages 616-623
Technical Paper | TMI-2: Remote Technology and Engineering / Nuclear Safety | doi.org/10.13182/NT89-A27713
Articles are hosted by Taylor and Francis Online.
The 1979 Three Mile Island Unit 2 accident caused fuel particles (fines) and debris to be transported throughout the reactor coolant system (RCS). Estimates of the fuel quantities in the RCS outside the reactor vessel boundary (defined as ex-vessel areas) have been developed. These estimates, in conjunction with as-low-as-reasonably-achievable considerations, were used to determine which ex-vessel areas required defueling.
