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Title: Summary of Grizzly Development for Advanced Reactor Structural Materials

Abstract

This summary report contains an overview of work performed during Fiscal Year 2019 under the Nuclear Engineering Advanced Modeling and Simulation (NEAMS) Fuels Product Line work package entitled "MS-19IN020106 - GRIZZLY - INL". Grizzly is a code based on the MOOSE framework that has been under development for several years funded by the US Department of Energy’s Light Water Reactor Sustainability (LWRS) program. Prior to 2019, Grizzly development was focused on development of capabilities needed to simulate the effects of aging mechanisms in light water reactor (LWR) components. The goal of this LWR-focused work has been to develop tools that can be used to assess the ability of existing LWRs to perform safety in long term operation (LTO) scenarios. This LWR-focused work has primarily focused on the effects of reactor pressure vessel (RPV) embrittlement and aging of reinforced concrete structures. Grizzly development to support LWR degradation needs is still ongoing, but starting in 2019, Grizzly’s capabilities are being expanded to also meet growing needs for a tool to address structural component integrity and degradation in advanced reactors. A simulation capability for advanced reactor components has many of the same basic requirements that one for LWRs does, such as the abilitymore » to solve coupled systems of partial differential equations that arise from the fact that many of the problems of interest involve multiple coupled physics. The materials issues also inherently involve multiple length scales, with the response at the engineering scale being strongly affected by mechanisms occurring at atomistic and mesoscopic scales.« less

Authors:
ORCiD logo [1]; ORCiD logo [1];  [2];  [3]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Laboratory
  2. Temple University
  3. Utah State University
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1572400
Report Number(s):
INL/EXT-19-55958-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; High Temperature Materials; Grizzly; XFEM; Fracture; Advanced Reactors; Structural Materials

Citation Formats

Spencer, Benjamin W, Pitts, Stephanie A, Liu, Ling, Vyas, Manu, Jiang, Wen, Casagranda, Albert, and McDowell, Dylan James. Summary of Grizzly Development for Advanced Reactor Structural Materials. United States: N. p., 2019. Web. doi:10.2172/1572400.
Spencer, Benjamin W, Pitts, Stephanie A, Liu, Ling, Vyas, Manu, Jiang, Wen, Casagranda, Albert, & McDowell, Dylan James. Summary of Grizzly Development for Advanced Reactor Structural Materials. United States. doi:10.2172/1572400.
Spencer, Benjamin W, Pitts, Stephanie A, Liu, Ling, Vyas, Manu, Jiang, Wen, Casagranda, Albert, and McDowell, Dylan James. Mon . "Summary of Grizzly Development for Advanced Reactor Structural Materials". United States. doi:10.2172/1572400. https://www.osti.gov/servlets/purl/1572400.
@article{osti_1572400,
title = {Summary of Grizzly Development for Advanced Reactor Structural Materials},
author = {Spencer, Benjamin W and Pitts, Stephanie A and Liu, Ling and Vyas, Manu and Jiang, Wen and Casagranda, Albert and McDowell, Dylan James},
abstractNote = {This summary report contains an overview of work performed during Fiscal Year 2019 under the Nuclear Engineering Advanced Modeling and Simulation (NEAMS) Fuels Product Line work package entitled "MS-19IN020106 - GRIZZLY - INL". Grizzly is a code based on the MOOSE framework that has been under development for several years funded by the US Department of Energy’s Light Water Reactor Sustainability (LWRS) program. Prior to 2019, Grizzly development was focused on development of capabilities needed to simulate the effects of aging mechanisms in light water reactor (LWR) components. The goal of this LWR-focused work has been to develop tools that can be used to assess the ability of existing LWRs to perform safety in long term operation (LTO) scenarios. This LWR-focused work has primarily focused on the effects of reactor pressure vessel (RPV) embrittlement and aging of reinforced concrete structures. Grizzly development to support LWR degradation needs is still ongoing, but starting in 2019, Grizzly’s capabilities are being expanded to also meet growing needs for a tool to address structural component integrity and degradation in advanced reactors. A simulation capability for advanced reactor components has many of the same basic requirements that one for LWRs does, such as the ability to solve coupled systems of partial differential equations that arise from the fact that many of the problems of interest involve multiple coupled physics. The materials issues also inherently involve multiple length scales, with the response at the engineering scale being strongly affected by mechanisms occurring at atomistic and mesoscopic scales.},
doi = {10.2172/1572400},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

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