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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
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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The blossoming of cooperation between the U.S. and Canada
The United States and Canadian nuclear industries used to be an example of how two independent teams of engineers facing an identical problem—making electricity from uranium—could come up with completely different answers. In the 1950s, Canada began designing a reactor with tubes, heavy water, and natural uranium, while in the U.S. it was big pots of light water and enriched uranium.
But 80 years later, there is a remarkable convergence. The North American push for a new generation of nuclear reactors, mostly small modular reactors (SMRs), is becoming binational, with U.S. and Canadian companies seeking markets and regulatory certification on both sides of the border and in many cases sourcing key components in the other country.
D. Ostermann, C. Krumb, R. Krieg
Nuclear Science and Engineering | Volume 179 | Number 2 | February 2015 | Pages 211-231
Technical Paper | doi.org/10.13182/NSE14-3
Articles are hosted by Taylor and Francis Online.
During postulated severe accidents in nuclear power plants, steel sheets and shells may suffer high plastic strains up to several percent. In contrast, for design-basis accidents the strains are within lower limits of the order of 0.2% required by the given rules. In both cases the margins up to structural fracture are of vital interest. In sheets and shells these margins may be reduced by diffuse as well as localized necking. Therefore, this paper investigates the remaining structural deformability described by the uniform elongation strain, where diffuse necking starts, and the quasi-uniform elongation strain, where localized necking starts. The theoretical models developed recently for thin sheets under uniaxial loading are extended to account for biaxial loading. Major findings are confirmed by appropriate structural experiments. Based on these results and their scatter, strain limits are recommended for steel sheets and shells under accident loading, such that fracture can be excluded. The strains caused by the accidents discussed in this paper turn out to be below these limits.
