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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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June 2024
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Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.