ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Tomohiko Tamaki, Masanori Ohtani, Yasuharu Kawabe
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 216-224
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3026
Articles are hosted by Taylor and Francis Online.
A steam generator tube rupture (SGTR) incident occurred in Mihama Unit 2 on February 9, 1991. This is the first SGTR incident where the emergency core cooling system was actuated in Japan. With some measures being taken to improve the model, the precise simulation of the SGTR using RETRAN-02/MOD4 was conducted. A nonequilibrium model was applied to the secondary side of the damaged SG to obtain a reasonable response of the secondary pressure. The model of the reactor upper head was improved to simulate void generation during reactor coolant system depressurization, and there was good agreement with the actual plant data.