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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Theo G. Theofanous, Hongfei Yan
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 332-353
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34793
Articles are hosted by Taylor and Francis Online.
This is the second part of a three-part series of papers addressing the probability of liner failure in a Mark-I containment. The purpose is to quantify melt release and spreading phenomena in a form suitable for use in the probabilistic framework as discussed in the first part of this series. The quantification of melt release parameters (quantity, superheat, and zirconium content) is derived from an assessment of available system code results and certain independent auxiliary considerations of the physics of the meltdown and slumping processes in the relevant geometries. The quantification of melt spreading phenomena is based primarily on simulant scaled experiments run specifically for this purpose; however, auxiliary considerations of the physics of operative cooling and quenching mechanisms also play a significant role in this assessment.