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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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
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.
Gary M. Stange, Michael Corradini, Robert Swader, George Petry, Thomas R. Mackie, Kevin W. Eliceiri
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 191-200
Technical Paper | doi.org/10.13182/NT16-107
Articles are hosted by Taylor and Francis Online.
Uranyl nitrate hexahydrate [UO2(NO3)2 · 6H2O] (UNH) holds interest as a potential nuclear reactor fuel for manufacturing the key medical isotope 99mTc through the production and subsequent decay of 99Mo. Fuel element design for such a production method requires knowledge of the thermal properties of the fuel material, particularly in the case of UNH, which has a significantly lower melting temperature than that of fuels being used currently. A system was designed to measure the thermal conductivity of UNH by an ASTM International standard thermal probe method. Measurements were made at four temperatures within the relevant range for the reactor system (25°C through 55°C) and with a variety of material preparations. With a fill gas of air, the results demonstrate a thermal conductivity at 25°C between 0.07 and 0.10 W · cm−1 · K−1. The results are the first step toward future studies that could lead to a more efficient reactor design with a heating source term capable of meeting the demand for 99Mo production while maintaining a safe and effective thermal margin.