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Title: Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures

Abstract

The Grizzly code has been under development for the U.S. Department of Energy’s Light Water Reactor Sustainability program to provide predictive tools for the evolution of material degradation in critical light water reactor structural components due to long-term exposure to the environmental conditions of normal reactor operation, and for the effects of this degradation on the safety of these components. This development has primarily targeted reactor pressure vessels and reinforced concrete structures. Work performed during Fiscal Year 2019 added important features for both of these types of structures. For probabilistic fracture mechanics analysis of reactor pressure vessels, capabilities were added to account for the effects of warm prestressing and residual stresses, as well as to model crack initiation, growth, and arrest. For modeling microstructure evolution in reactor pressure vessels, a cluster dynamics model for evolution of Mn-Ni-Si phases has been implemented. For modeling degraded reinforced concrete structures, capabilities to consider the combined effects of damage and creep in the concrete constitutive model and model nonlinear behavior of reinforcing bars has been added. These newly-developed features fill important gaps in Grizzly’s feature set for engineering-scale analysis of degraded reactor pressure vessels and reinforced concrete structures. Grizzly development in both of thesemore » areas has reached a point where it is ready for extensive testing on relevant engineering problems.« less

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1572397
Report Number(s):
INL/EXT-19-56012-Rev000
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 - GENERAL STUDIES OF NUCLEAR REACTORS; 97 - MATHEMATICS AND COMPUTING; Grizzly; Reinforced Concrete; Reactor Pressure Vessel; Fracture Mechanics; Cluster Dynamics

Citation Formats

Spencer, Benjamin W, Hoffman, William M, Schwen, Daniel, and Biswas, Sudipta. Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures. United States: N. p., 2019. Web. doi:10.2172/1572397.
Spencer, Benjamin W, Hoffman, William M, Schwen, Daniel, & Biswas, Sudipta. Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures. United States. doi:10.2172/1572397.
Spencer, Benjamin W, Hoffman, William M, Schwen, Daniel, and Biswas, Sudipta. Mon . "Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures". United States. doi:10.2172/1572397. https://www.osti.gov/servlets/purl/1572397.
@article{osti_1572397,
title = {Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures},
author = {Spencer, Benjamin W and Hoffman, William M and Schwen, Daniel and Biswas, Sudipta},
abstractNote = {The Grizzly code has been under development for the U.S. Department of Energy’s Light Water Reactor Sustainability program to provide predictive tools for the evolution of material degradation in critical light water reactor structural components due to long-term exposure to the environmental conditions of normal reactor operation, and for the effects of this degradation on the safety of these components. This development has primarily targeted reactor pressure vessels and reinforced concrete structures. Work performed during Fiscal Year 2019 added important features for both of these types of structures. For probabilistic fracture mechanics analysis of reactor pressure vessels, capabilities were added to account for the effects of warm prestressing and residual stresses, as well as to model crack initiation, growth, and arrest. For modeling microstructure evolution in reactor pressure vessels, a cluster dynamics model for evolution of Mn-Ni-Si phases has been implemented. For modeling degraded reinforced concrete structures, capabilities to consider the combined effects of damage and creep in the concrete constitutive model and model nonlinear behavior of reinforcing bars has been added. These newly-developed features fill important gaps in Grizzly’s feature set for engineering-scale analysis of degraded reactor pressure vessels and reinforced concrete structures. Grizzly development in both of these areas has reached a point where it is ready for extensive testing on relevant engineering problems.},
doi = {10.2172/1572397},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

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