ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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Saskatchewan government provides C$80 million for eVinci demonstration
Saskatchewan premier Scott Moe yesterday announced C$80 million (about $59 million) for the Saskatchewan Research Council (SRC) to pursue demonstration of Westinghouse Electric Company’s eVinci microreactor technology.
Ernie Kee, John Hasenbein, Alex Zolan, Phil Grissom, Seyed Reihani, Zahra Mohaghegh, Fatma Yilmaz, Bruce Letellier, Vera Moiseytseva, Rodolfo Vaghetto, David Imbaratto, Tatsuya Sakurahara
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 270-291
Technical Paper | doi.org/10.13182/NT16-34
Articles are hosted by Taylor and Francis Online.
An approach is described that would use test data to evaluate the risk associated with the concerns raised in Generic Safety Issue 191 (GSI-191). The relationship to the elements of quantitative risk-informed regulation for addressing the concerns raised in GSI-191 in pressurized water reactor (PWR) plant licensing is described. Use of experimental data from a deterministic sump performance test to establish scenario success for tested debris loads is summarized and compared to the licensing requirements in the regulations. Generation and transport of debris to the emergency core cooling system sump from a loss-of-coolant accident is described, and data are shown for a particular PWR. Application of the analysis results to a license amendment for an operating PWR is summarized.