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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.”
Michael D. Allen, Harlan W. Stockman, Kenneth O. Reil, Arthur J. Grimley
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 214-228
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34472
Articles are hosted by Taylor and Francis Online.
High-burnup uranium dioxide reactor fuel was heated in-pile at ∼2490 K in a reducing atmosphere (33% H2 in argon) for 16 min. Fission product aerosols and vapors released from the fuel were collected on a series of sequentially opened filters; the fractions of the original fuel inventory collected on the filters were f Cs = 0.56, f I = 0.38, f Ba = 0.078, f Sr = 0.053, f Eu = 0.064, and f Te < 0.002. The measured release rates for nonvolatile fission products were much higher than predicted by existing release codes, whereas tellurium release was much lower. Posttest examination of the fuel indicates extensive fuel/clad interaction, fuel swelling, and infiltration of the fuel by a zirconium-rich metallic melt; this melt kept oxygen potentials in the fuel very low. The low oxygen potentials and fuel disruption may account for the discrepancy between release codes and the test release results.