Multiple Degradation Mechanisms in Reinforced Concrete Structures, Modeling and Risk Analysis
Creators
- 1. University of Houston, TX (United States)
- 2. University of Southern California, Los Angeles, CA (United States)
- 3. University of Colorado, Boulder, CO (United States)
Description
The overarching goal of this project is to complement ongoing Department of Energy (DOE) Light Water Reactor Sustainability (LWRS)-funded Grizzly concrete modeling development efforts by providing improved multi-physics models for incorporation into the Grizzly and BlackBear codes. Objectives of this work identified at the outset of this project include: 1. Coupling between mechanical damage and transport processes. The mechanical damage will be characterized by nonlinear mechanical constitutive models appropriate for concrete used in nuclear power plants (NPPs). 2. Improved representation of the coupling among the transport process, building on the current moisture and thermal transport models in Grizzly. The parameters for coupling among heat and mass transport in the multi-physics model will be experimentally determined. 3. Coupling among different scale levels of concrete constituents, fine and coarse aggregates, cement paste, hydration products, and pore structure. 4. Probabilistic analysis of the random nature of the heterogeneous concrete structure and the environmental factors (ambient temperature and humidity) and their multiple effects on concrete deterioration. 5. Benchmark verification, validation and uncertainty quantification of the thermo-hygro- chemo-mechanical (THCM) concrete formulation. The end goal of this work was to provide a comprehensive and robust simulation capability that can be applied at the engineering scale for analysis of realistic deterioration scenarios in NPP concrete structures.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1599377; https://www.osti.gov/biblio/1599377; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo periodAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- 218 p.
- Report number
- INL-EXT--20-57095-Rev000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 55006351
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; NONLINEAR PROBLEMS; NUCLEAR POWER PLANTS; PORE STRUCTURE; PROBABILISTIC ESTIMATION; REINFORCED CONCRETE; RISK ASSESSMENT; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- BUILDING MATERIALS; CALCULATION METHODS; COMPOSITE MATERIALS; CONCRETES; MATERIALS; MICROSTRUCTURE; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; REINFORCED MATERIALS; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- Contract AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- OSTIID--1599377