Assessment of SiC-CMC compatibility with components of actinide fuel systems

Tyler J. Gerczak; Jake W. McMurray

doi:10.1016/j.anucene.2018.12.030

Assessment of SiC-CMC compatibility with components of actinide fuel systems

Tyler J. Gerczak, Jake W. McMurray

Particle Fuel Forms

Research output: Contribution to journal › Review article › peer-review

5 Scopus citations

Abstract

Silicon carbide (SiC) fiber reinforced SiC ceramic matrix composites (CMC) represent an alternative cladding material for accident tolerant fuel light water reactor (LWR) applications, however, data and technology gaps exist that need to be understood before SiC-CMCs can be considered. One technology gap is the understanding of fuel-clad chemical interactions (FCCI) in SiC-CMC clad LWR systems. A review of SiC interactions with relevant elements to the LWR fuel system is discussed. Insights are drawn from research focusing on the use of SiC for high temperature electronics applications and high temperature structural materials applications as well as insights from tristructural-isotropic (TRISO) coated particle fuel development, where SiC is a critical component of the TRISO design. The interactions discussed in this review are framed relative to the expected conditions for SiC-CMC cladding application. The general observation is that limited risk of FCCI exists under normal operating conditions for SiC-CMC cladding systems in LWR applications.

Original language	English
Pages (from-to)	127-139
Number of pages	13
Journal	Annals of Nuclear Energy
Volume	128
DOIs	https://doi.org/10.1016/j.anucene.2018.12.030
State	Published - Jun 2019

Funding

The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology R&D program in the Office of Nuclear Energy, US Department of Energy. The work presented in this paper was supported by the Advanced Fuels Campaign of the Nuclear Technology R&D program in the Office of Nuclear Energy, US Department of Energy.

Funders	Funder number
US Department of Energy
U.S. Department of Energy
Office of Nuclear Energy

Keywords

Accident tolerant fuel
Ceramic matrix composites
Light water reactor
Silicon carbide

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10.1016/j.anucene.2018.12.030

Cite this

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title = "Assessment of SiC-CMC compatibility with components of actinide fuel systems",

abstract = "Silicon carbide (SiC) fiber reinforced SiC ceramic matrix composites (CMC) represent an alternative cladding material for accident tolerant fuel light water reactor (LWR) applications, however, data and technology gaps exist that need to be understood before SiC-CMCs can be considered. One technology gap is the understanding of fuel-clad chemical interactions (FCCI) in SiC-CMC clad LWR systems. A review of SiC interactions with relevant elements to the LWR fuel system is discussed. Insights are drawn from research focusing on the use of SiC for high temperature electronics applications and high temperature structural materials applications as well as insights from tristructural-isotropic (TRISO) coated particle fuel development, where SiC is a critical component of the TRISO design. The interactions discussed in this review are framed relative to the expected conditions for SiC-CMC cladding application. The general observation is that limited risk of FCCI exists under normal operating conditions for SiC-CMC cladding systems in LWR applications.",

keywords = "Accident tolerant fuel, Ceramic matrix composites, Light water reactor, Silicon carbide",

author = "Gerczak, {Tyler J.} and McMurray, {Jake W.}",

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year = "2019",

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doi = "10.1016/j.anucene.2018.12.030",

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T1 - Assessment of SiC-CMC compatibility with components of actinide fuel systems

AU - Gerczak, Tyler J.

AU - McMurray, Jake W.

PY - 2019/6

Y1 - 2019/6

N2 - Silicon carbide (SiC) fiber reinforced SiC ceramic matrix composites (CMC) represent an alternative cladding material for accident tolerant fuel light water reactor (LWR) applications, however, data and technology gaps exist that need to be understood before SiC-CMCs can be considered. One technology gap is the understanding of fuel-clad chemical interactions (FCCI) in SiC-CMC clad LWR systems. A review of SiC interactions with relevant elements to the LWR fuel system is discussed. Insights are drawn from research focusing on the use of SiC for high temperature electronics applications and high temperature structural materials applications as well as insights from tristructural-isotropic (TRISO) coated particle fuel development, where SiC is a critical component of the TRISO design. The interactions discussed in this review are framed relative to the expected conditions for SiC-CMC cladding application. The general observation is that limited risk of FCCI exists under normal operating conditions for SiC-CMC cladding systems in LWR applications.

AB - Silicon carbide (SiC) fiber reinforced SiC ceramic matrix composites (CMC) represent an alternative cladding material for accident tolerant fuel light water reactor (LWR) applications, however, data and technology gaps exist that need to be understood before SiC-CMCs can be considered. One technology gap is the understanding of fuel-clad chemical interactions (FCCI) in SiC-CMC clad LWR systems. A review of SiC interactions with relevant elements to the LWR fuel system is discussed. Insights are drawn from research focusing on the use of SiC for high temperature electronics applications and high temperature structural materials applications as well as insights from tristructural-isotropic (TRISO) coated particle fuel development, where SiC is a critical component of the TRISO design. The interactions discussed in this review are framed relative to the expected conditions for SiC-CMC cladding application. The general observation is that limited risk of FCCI exists under normal operating conditions for SiC-CMC cladding systems in LWR applications.

KW - Accident tolerant fuel

KW - Ceramic matrix composites

KW - Light water reactor

KW - Silicon carbide

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U2 - 10.1016/j.anucene.2018.12.030

DO - 10.1016/j.anucene.2018.12.030

M3 - Review article

AN - SCOPUS:85059680458

SN - 0306-4549

VL - 128

SP - 127

EP - 139

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

ER -

Assessment of SiC-CMC compatibility with components of actinide fuel systems

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Keywords

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