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.
Gert Van den Eynde, Robert Beauwens, Ernest Mund
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 300-309
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2664
Articles are hosted by Taylor and Francis Online.
The boundary source method is an integral method introduced in the late 1960s for solving one-dimensional one-velocity transport problems arising in cell calculations. This method was further developed in various ways since that period and found to be of particular interest for recent applications to nodal transport codes. We have developed a boundary source code in plane geometry that allows for anisotropic scattering of arbitrary high order, and it is the purpose of this paper to display the extreme accuracy of this code, showing hereby that the boundary source method is probably the most accurate transport solution method available today for solving piecewise homogeneous transport problems.
