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  5. Impact of Fuel Rod Coatings on Reactor Performance and Safety
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Impact of Fuel Rod Coatings on Reactor Performance and Safety

Date Issued
May 1, 2015
Author(s)
Stewart, Ian Robert  
Advisor(s)
Laurence F. Miller
Additional Advisor(s)
Brian Wirth
Ronald Pevey
Permanent URI
https://trace.tennessee.edu/handle/20.500.14382/39448
Abstract

This study evaluates the use of a ceramic coating on the Zr-alloy cladding within a PWR using four ceramic compounds of 5 and 10 micron thicknesses: ZrO2, TiAlN, Ti2AlC, and Ti3AlC2. The film’s impact is assessed for variation on: reactivity, fuel cycle length, maximum temperature, film’s roughness, and transient conditions. The reactivity is analyzed using the following methods: change in the multiplication factor (k) each film introduces to the system using the ABH method, and Monte Carlo software (MCNP). Both methods are in good agreement, yielding less than half a percent change from a reference, no-film fuel pin. In order from lowest impact to highest impact on reactivity, the films are as follows for 10 micron thickness: ZrO2 (0.06%), TiAlN (0.20%), Ti3AlC2 (0.21%), and Ti2AlC (0.25%). This change directly impacts the fuel cycle length of the fuel. A linear reactivity model is used to approximate the loss in fuel cycle length and final burnup for a reference cycle of 300 days and 50 MWd/kg, respectively. The estimated loss in days is less than a day for all 5-micron films and less than 3 days for all 10 micron films (highest: 2.25 days, Ti2AlC) with all burnup calculations around 48.50 MWd/kg for all films. The impact the film yields on the temperature of the fuel pin is calculated using the one-dimensional thermal resistance circuit for each region (fuel, gap, clad, film, and moderator). The films’ thermal conductivity will directly impact this calculation, yet for the thin ceramic films, the percent change from a reference fuel is less 1% for all films at both thicknesses (largest change, lowest thermal conductivity: ZrO2). The roughness of the films currently being deposited is around 10 microinch Ra. This value is used with two perturbations, 5 microinches and 15 microinches, to evaluate the impact on the heat transfer coefficient and the induced friction-loss (pressure). For all roughness values the heat transfer coefficient stays well within typical PWR values while inducing a smaller pressure drop along the channel (compared to Zr-alloy clad). The thermal analysis is used to simulate a transient by varying the linear power density and the coolant flow rate. These two parameters are varied at different rates to impose a momentary mismatch in the system. In all simulations, the film reacts almost identical of that of the Zr-alloy clad reference model.

Subjects

nuclear engineering

nuclear fuel

accident tolerant fue...

ceramic film

ceramic coating on cl...

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

Ian_Stewart___Nuclear_Eng._Master_s_Thesis.pdf

Size

16.36 MB

Format

Adobe PDF

Checksum (MD5)

99c04de2c2e144918c3375a45e48bdf9

Thumbnail Image
Name

Ian_Stewart___Nuclear_Eng._Master_s_Thesis_Final.docx

Size

2.43 MB

Format

Microsoft Word XML

Checksum (MD5)

afd8f9fb41cba07140922f81403fd364

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