Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis

Singh, Gyanender; Terrani, Kurt; Katoh, Yutai

doi:10.1016/j.jnucmat.2017.11.004

Title: Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis

Authors:: Singh, Gyanender; Terrani, Kurt; Katoh, Yutai

Publication Date:: Thu Feb 01 00:00:00 EST 2018

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1505854

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Name: Journal of Nuclear Materials Journal Volume: 499 Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Citation Formats


                    Singh, Gyanender, Terrani, Kurt, and Katoh, Yutai. Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis.  Netherlands: N. p., 2018. 
Web.  doi:10.1016/j.jnucmat.2017.11.004.

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                    Singh, Gyanender, Terrani, Kurt, & Katoh, Yutai. Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis.  Netherlands.  https://doi.org/10.1016/j.jnucmat.2017.11.004

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                    Singh, Gyanender, Terrani, Kurt, and Katoh, Yutai. Thu .  
"Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis".  Netherlands.  https://doi.org/10.1016/j.jnucmat.2017.11.004.

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@article{osti_1505854,

  title        = {Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis},

  author       = {Singh, Gyanender and Terrani, Kurt and Katoh, Yutai},

  abstractNote = {},

  doi          = {10.1016/j.jnucmat.2017.11.004},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 499,

  place        = {Netherlands},

  year         = {Thu Feb 01 00:00:00 EST 2018},

  month        = {Thu Feb 01 00:00:00 EST 2018}

}

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Title: Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis

Citation Formats

Stability of SiC and its composites at high neutron fluence journal, October 2011

Multidimensional multiphysics simulation of nuclear fuel behavior journal, April 2012

Accident tolerant fuels for LWRs: A perspective journal, May 2014

Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding journal, November 2015

Kinetics and Mechanisms of High-Temperature Creep in Silicon Carbide: II, Chemically Vapor Deposited journal, November 1984

Handbook of SiC properties for fuel performance modeling journal, September 2007

Characterization of SiC–SiC composites for accident tolerant fuel cladding journal, November 2015

Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature journal, March 2016

Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment journal, September 2015

Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application journal, December 2015

Damage accumulation and annealing in 6H–SiC irradiated with Si+ journal, September 1998

Radiation effects in SiC for nuclear structural applications journal, June 2012

Evaluation of neutron irradiated near-stoichiometric silicon carbide fiber composites journal, December 2000

Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors journal, January 2015

Annealing Behavior of Neutron-Irradiated Silicon Carbide Temperature Monitors journal, December 1972

Swelling of SiC at intermediate and high irradiation temperatures journal, August 2007

Observation and possible mechanism of irradiation induced creep in ceramics journal, March 2013

Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation journal, October 2015

Chemically vapor deposited silicon carbide (SiC) for optical applications journal, May 1990

Thermo-mechanical analysis of LWR SiC/SiC composite cladding journal, April 2014

Effects of Thermal Annealing on the Macroscopic Dimension and Lattice Parameter of Heavily Neutron-Irradiated Silicon Carbide journal, July 1992

Thermal properties of neutron-irradiated SiC; effects of boron doping journal, July 1982

Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures journal, August 2010

Mechanical, Thermal, and Microstructural Properties of Neutron-Irradiated SiC journal, July 1983

Re-defining failure envelopes for silicon carbide composites based on damage process analysis by acoustic emission journal, October 2013

A structural model for multi-layered ceramic cylinders and its application to silicon carbide cladding of light water reactor fuel journal, March 2015

Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects journal, May 2014

Limits on irradiation-induced thermal conductivity and electrical resistivity in silicon carbide materials journal, August 2004

Silicon Carbide Oxidation in Steam up to 2 MPa journal, July 2014

Effect of irradiation damage on hydrothermal corrosion of SiC journal, September 2015

Thermal conductivity of neutron-irradiated pyrolytic β-silicon carbide journal, April 1973

Dimensional Stability and Strength of Neutron-Irradiated SiC-Based Fibers journal, December 1996

Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation journal, April 2005

Finite rotation effects in numerical integration of rate constitutive equations arising in large-deformation analysis journal, December 1980

Investigations on ceramic materials for fusion technology journal, November 1990

Grain size dependence of the thermal conductivity of polycrystalline chemical vapor deposited β‐SiC at low temperatures journal, December 1990

Design, preparation and properties of non-oxide CMCs for application in engines and nuclear reactors: an overview journal, February 2004

Mechanical and thermal properties of SiCf/SiC composites irradiated with neutrons at high temperatures journal, November 2005

Stability of SiC and its composites at high neutron fluence
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Multidimensional multiphysics simulation of nuclear fuel behavior
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journal, November 2015

Kinetics and Mechanisms of High-Temperature Creep in Silicon Carbide: II, Chemically Vapor Deposited
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Handbook of SiC properties for fuel performance modeling
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Characterization of SiC–SiC composites for accident tolerant fuel cladding
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Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature
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Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment
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Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application
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Damage accumulation and annealing in 6H–SiC irradiated with Si+
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Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
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Annealing Behavior of Neutron-Irradiated Silicon Carbide Temperature Monitors
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journal, August 2007

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journal, March 2013

Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation
journal, October 2015

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Effects of Thermal Annealing on the Macroscopic Dimension and Lattice Parameter of Heavily Neutron-Irradiated Silicon Carbide
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Thermal properties of neutron-irradiated SiC; effects of boron doping
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Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures
journal, August 2010

Mechanical, Thermal, and Microstructural Properties of Neutron-Irradiated SiC
journal, July 1983

Re-defining failure envelopes for silicon carbide composites based on damage process analysis by acoustic emission
journal, October 2013

A structural model for multi-layered ceramic cylinders and its application to silicon carbide cladding of light water reactor fuel
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Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
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Limits on irradiation-induced thermal conductivity and electrical resistivity in silicon carbide materials
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Silicon Carbide Oxidation in Steam up to 2 MPa
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Effect of irradiation damage on hydrothermal corrosion of SiC
journal, September 2015

Thermal conductivity of neutron-irradiated pyrolytic β-silicon carbide
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Finite rotation effects in numerical integration of rate constitutive equations arising in large-deformation analysis
journal, December 1980

Investigations on ceramic materials for fusion technology
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