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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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May 2025
Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
Yutaka Furuta, Yoshihiko Kanemori
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 261-267
Technical Paper | doi.org/10.13182/NSE67-A17336
Articles are hosted by Taylor and Francis Online.
Gamma-ray dose rates from a 60Co cylindrical source were obtained experimentally in the radial direction at the half-height of the source. The concept of the dose buildup factor was introduced for a volume source. The dose buildup factor for a cylindrical source, which is represented as a function of the distance between source and detection point, has a value of about five at the point nearest to the source surface. The factor then decreases rapidly, passes through a minimum value, and approaches a constant value. These features were analyzed experimentally with a line and a disk source. An empirical formula for the dose buildup factor is proposed which agrees with the experimental values to within about ± 15%.
