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Channel gap measurments in nuclear plate fuel

Authors: James Smith (Idaho National Laboratory) , Casey Jesse (Idaho National Laboratory) , Margaret Marshall (Idaho National Laboratory) , Clark Scott (Idaho National Laboratory) , David Cottle (Idaho National Laboratory)

  • Channel gap measurments in nuclear plate fuel

    None

    Channel gap measurments in nuclear plate fuel

    Authors: , , , ,

Abstract

The U.S. High-Performance Research Reactors (USHPRR) program is developing new Low Enriched Uranium (LEU) U-Mo Fuel and testing the performance of the plate fuel. The primary fuel design is based on uranium-molybdenum (U-Mo) foil clad in an aluminum alloy that are in the form of mini-plate specimens (1" x 4” plates). The fuel plates will be placed in a capsule in four layers with two plates per layer. The experiment is designed in such a way that the gaps between the U-Mo fuel plates are ultrasonically measured after each irradiation cycle. Irradiation has taken place at the ATR (Advance Test Reactor). Geometry changes in the fuel plates is an important performance indicator

How to Cite:

Smith, J., Jesse, C., Marshall, M., Scott, C. & Cottle, D., (2019) “Channel gap measurments in nuclear plate fuel”, Review of Progress in Quantitative Nondestructive Evaluation .

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Published on
03 Dec 2019
Peer Reviewed
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