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  5. Kinetic and Thermodynamic Modeling of Long Term Phase Stability in Alloy 800H Subjected to LWR Core Conditions
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Kinetic and Thermodynamic Modeling of Long Term Phase Stability in Alloy 800H Subjected to LWR Core Conditions

Date Issued
December 1, 2015
Author(s)
Pratt, Wayne Ethan  
Advisor(s)
Steven J. Zinkle
Additional Advisor(s)
Brian D. Wirth
Kurt E. Sickafus
Permanent URI
https://trace.tennessee.edu/handle/20.500.14382/39659
Abstract

An in depth literature review of Incoloy Alloy 800H was conducted and presented to summarize the current understanding of microstructural evolution under irradiation and secondary phase precipitate stability. Due to a lack of radiation induced segregation (RIS) data for Alloy 800H, Isopleth sections varying Cr, Ni, Ti, and Si were generated from a computational thermodynamics approach using ThermoCalc and analyzed to compensate for knowledge related to radiation induced precipitates (RIP’s). These isopleths were analyzed for a composition range based off previous knowledge of RIS tendencies in austenitic stainless steels. Analysis of four major binary phase diagrams and complex phase diagrams calculated through ThermoCalc and MatCalc were used to simulate the precipitation kinetics during the lifetime of Incoloy Alloy 800H used in a light water reactor (LWR) core setting. These aging simulations were then conducted using the MatCalc heat treatments tool with M23C6 [Chromium Carbide], Sigma, and Ni3Ti [Gamma Prime] set as the precipitates of interest.


A discrepancy was found relating to the presence of sigma phase at low temperatures between ThermoCalc and MatCalc complex phase diagram calculations. Several minor phases were noted from the complex phase diagrams and isopleths for further research. Isopleth sections revealed that no major RIP’s should form given the current assumption of RIS behavior. Simulations of precipitation kinetics predict a precipitate coarsening somewhere between 6-7 years of operation for M23C­6 [Chromium Carbide] precipitates. This results in a decline in number density and an increase in precipitate size. Anticipated radiation induced segregation has very little effect on M23C6­ [Chromium Carbide] precipitate size, however increasing RIS results in the formation of fewer M23C6 [Chromium Carbide] precipitates. Sigma phase is found to increase in amount and decrease in size as segregation increases until the number of precipitates reaches a maximum between 20.42 and 14.42 wt% Cr. At doses greater than this the density of sigma precipitates is expected to decrease while the size of precipitates is expected to remain consistent.

Subjects

Phase Stability

800H

Kinetic Modeling

Thermodynamic Modelin...

Reactor Core

Light Water Reactor

Disciplines
Materials Science and Engineering
Nuclear Engineering
Other Materials Science and Engineering
Degree
Master of Science
Major
Materials Science and Engineering
Embargo Date
January 1, 2011
File(s)
Thumbnail Image
Name

Thesis_Ethan_Pratt.pdf

Size

2.98 MB

Format

Adobe PDF

Checksum (MD5)

6df3c8a05cb4b2fddbe4cbc43c3b09c1

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