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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Jong Hwi Jeong, Sungkoo Cho, Choonsik Lee, Kun-Woo Cho, Chan Hyeong Kim
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 227-230
Phantoms | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Radiation Protection | doi.org/10.13182/NT09-A9130
Articles are hosted by Taylor and Francis Online.
In the present study, a high-quality voxel model of a Korean adult male was converted to a surface model based on polygon and nonuniform rational B-spline surfaces. The polygon model of the body surface was then modified in the back and buttock regions for some correction and finally converted back to a voxel model for Monte Carlo dose calculations. The dose calculation results showed that the modification of the back and buttock significantly changed the calculated dose values of the lungs and breasts for the postero-anterior irradiation geometry; the maximum difference, found for the lungs, was as large as 40% for the photon energy of 30 keV, even though the difference decreases with the photon energy.