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.
Yoshitomo Uwamino, Takashi Nakamura, Kazuo Shin
Nuclear Science and Engineering | Volume 80 | Number 3 | March 1982 | Pages 360-369
Technical Paper | doi.org/10.13182/NSE82-A19820
Articles are hosted by Taylor and Francis Online.
Attenuation of neutrons and photons transmitted through graphite, iron, water, and ordinary concrete assemblies were studied by spectral measurements using an NE-213 organic scintillation detector with an (n-γ) discrimination technique. Source neutrons and photons were produced by 52-MeV proton bombardment of a 21.4-mm-thick graphite target placed in front of the assembly. The distributions of the light output from the scintillator following activation by neutrons and photons were unfolded by the revised FERDO code. These experimental results were used as benchmark data on neutron and photon penetration by neutrons of energy above 15 MeV. Multigroup Monte Carlo and one-dimensional ANISN transport calculations were performed with the DLC-58/HELLO group cross sections to compare with the measurement and to evaluate the cross sections. The results of the ANISN calculation of neutrons in slab geometry and the three-dimensional Monte Carlo calculation agreed with the experimental values except for high energy neutrons transmitted through water and graphite. The agreement of both calculations was well within the accuracy of 7% in the measured attenuation coefficients for graphite, iron, and water, and <10% for concrete. For photons, the ANISN calculation gave >20% over-estimation of the attenuation coefficients in the case of deep penetration through the medium for which the photon mean-free-path is shorter than that of neutrons, such as in iron and concrete. The secondary photons produced by the neutron-nucleus reactions are dominant compared with the primary photons, but otherwise the ANISN calculations gave good results.