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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.
M. Dion, G. Marleau
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 186-198
Technical Paper | doi.org/10.13182/NSE13-90
Articles are hosted by Taylor and Francis Online.
A method is proposed to evaluate implicit sensitivity coefficients for several types of reactor lattices, including pressurized water reactors and CANDU (CANada Deuterium Uranium) reactors, with different resonant and light isotope contents. The implicit sensitivity of the multiplication factor, resulting from a variation of an isotope density through the self-shielded cross sections, is computed for different cases. The precision of the method, the importance of the implicit coefficients with respect to the total sensitivity, and the contributions of all the isotopes are discussed and compared for the different systems. We also show how to compute the sensitivity coefficients in the unresolved energy groups, where the details of the resonances are not known. An equivalent dilution model is used for the self-shielding calculations. Complete transport calculations, using a collision probability method, are also used to compute reference values for the implicit sensitivities.