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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
The RAIN scale: A good intention that falls short
Radiation protection specialists agree that clear communication of radiation risks remains a vexing challenge that cannot be solved solely by finding new ways to convey technical information.
Earlier this year, an article in Nuclear News described a new radiation risk communication tool, known as the Radiation Index, or, RAIN (“Let it RAIN: A new approach to radiation communication,” NN, Jan. 2025, p. 36). The authors of the article created the RAIN scale to improve radiation risk communication to the general public who are not well-versed in important aspects of radiation exposures, including radiation dose quantities, units, and values; associated health consequences; and the benefits derived from radiation exposures.
Arthur A. Bauer
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 65-70
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Fuel | doi.org/10.13182/NT72-A31099
Articles are hosted by Taylor and Francis Online.
A fuel-specimen model is developed to describe the diametral swelling behavior of W-Re clad, oxide fuel specimens irradiated at a clad surface temperature in excess of 1200°C. The model is based on experimental observations at elevated fuel temperatures that fission-gas bubbles form to expand the fuel but that bubble and lenticular void movement, as a result of vaporphase transport, provide a mechanism for redensifying the fuel so that swelling is a continuous steady-state process. Good agreement with experimentally measured diametral changes is obtained by application of the model.