GRIZZLY: Nuclear Plant System Degradation Modeling

Simulates degradation and performance of nuclear plant components, focusing on reactor pressure vessels and concrete structures.
Technology No. CW-13-05

Grizzly models the degradation due to normal operating conditions of nuclear power plant systems, structures, and components. The code also simulates the ability of degraded components to safely perform under a variety of conditions. Grizzly can be applied to a variety of components. However, its development focused initially on the embrittlement of reactor pressure vessels and concrete structures. Vessels can degrade and facture due to irradiation and high temperatures, while concrete can degrade due to expansive alkali-silica reactions. Grizzly has capability to model the performance effect of these and other mechanisms.

This software is a controlled nuclear code, subject to a special release process due to its sensitive nature. To request access, please visit the Nuclear Computational Resource Center and create an account.

  • swap_vertical_circlemode_editAuthors (5)
    Idaho National Laboratory
    Virginia Polytechnic Institute and State University
    Benjamin Spencer
    Richard Martineau
    Bulent Biner
  • swap_vertical_circlecloud_downloadSupporting documents (1)
    Product brochure
    GRIZZLY: Nuclear Plant System Degradation Modeling.pdf
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