Deformation analysis of SiC-SiC channel box for BWR applications

G. Singh, J. Gorton, D. Schappel, Nicholas Brown, Y. Katoh, B. D. Wirth, K. A. Terrani

Research output: Contribution to journalArticle

Abstract

Silicon carbide fiber-reinforced silicon carbide matrix (SiC-SiC) composites are being considered as components in light water reactor cores to improve accident tolerance, including channel boxes and fuel cladding. In the nuclear reactor environment, core components like a channel box will be exposed to neutron and other radiation damage and temperature gradients. To ensure reliable and safe operation of a SiC-SiC channel box, it is important to assess its deformation behavior under in-reactor conditions including the expected neutron flux and temperature distributions. In particular, this work has evaluated the effect of non-uniform dimensional changes caused by spatially varying neutron flux and temperatures on the deformation behavior of the channel box over the course of one year. These analyses have been performed using the fuel performance modeling code BISON and the commercial finite element analysis code Abaqus, based on fast flux and temperature boundary conditions that have been calculated using the neutronics and thermal-hydraulics codes Serpent and CTF, respectively. The dependence of dimensions and thermophysical properties on fast flux and temperature has been incorporated into the material models. These initial results indicate significant bowing of the channel box with a lateral displacement greater than 6.5 mm. The channel box bowing behavior is time dependent and driven by the temperature dependence of the SiC irradiation-induced swelling and the neutron flux/fluence gradients. The bowing behavior gradually recovers during the course of the operating cycle as the swelling of the SiC-SiC material saturates. However, the bending relaxation due to temperature gradients does not fully recover and residual bending remains after the swelling saturates in the entire channel box.

LanguageEnglish (US)
Pages71-85
Number of pages15
JournalJournal of Nuclear Materials
Volume513
DOIs
StatePublished - Jan 1 2019

Fingerprint

Silicon carbide
silicon carbides
boxes
Bending (forming)
fibers
Neutron flux
Fibers
matrices
Swelling
flux (rate)
swelling
Thermal gradients
temperature gradients
Fluxes
Temperature
light water reactors
Light water reactors
Reactor cores
Radiation damage
reactor cores

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)

Cite this

Singh, G., Gorton, J., Schappel, D., Brown, N., Katoh, Y., Wirth, B. D., & Terrani, K. A. (2019). Deformation analysis of SiC-SiC channel box for BWR applications. Journal of Nuclear Materials, 513, 71-85. https://doi.org/10.1016/j.jnucmat.2018.10.045
Singh, G. ; Gorton, J. ; Schappel, D. ; Brown, Nicholas ; Katoh, Y. ; Wirth, B. D. ; Terrani, K. A. / Deformation analysis of SiC-SiC channel box for BWR applications. In: Journal of Nuclear Materials. 2019 ; Vol. 513. pp. 71-85.
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Singh, G, Gorton, J, Schappel, D, Brown, N, Katoh, Y, Wirth, BD & Terrani, KA 2019, 'Deformation analysis of SiC-SiC channel box for BWR applications' Journal of Nuclear Materials, vol. 513, pp. 71-85. https://doi.org/10.1016/j.jnucmat.2018.10.045

Deformation analysis of SiC-SiC channel box for BWR applications. / Singh, G.; Gorton, J.; Schappel, D.; Brown, Nicholas; Katoh, Y.; Wirth, B. D.; Terrani, K. A.

In: Journal of Nuclear Materials, Vol. 513, 01.01.2019, p. 71-85.

Research output: Contribution to journalArticle

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AU - Singh, G.

AU - Gorton, J.

AU - Schappel, D.

AU - Brown, Nicholas

AU - Katoh, Y.

AU - Wirth, B. D.

AU - Terrani, K. A.

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AB - Silicon carbide fiber-reinforced silicon carbide matrix (SiC-SiC) composites are being considered as components in light water reactor cores to improve accident tolerance, including channel boxes and fuel cladding. In the nuclear reactor environment, core components like a channel box will be exposed to neutron and other radiation damage and temperature gradients. To ensure reliable and safe operation of a SiC-SiC channel box, it is important to assess its deformation behavior under in-reactor conditions including the expected neutron flux and temperature distributions. In particular, this work has evaluated the effect of non-uniform dimensional changes caused by spatially varying neutron flux and temperatures on the deformation behavior of the channel box over the course of one year. These analyses have been performed using the fuel performance modeling code BISON and the commercial finite element analysis code Abaqus, based on fast flux and temperature boundary conditions that have been calculated using the neutronics and thermal-hydraulics codes Serpent and CTF, respectively. The dependence of dimensions and thermophysical properties on fast flux and temperature has been incorporated into the material models. These initial results indicate significant bowing of the channel box with a lateral displacement greater than 6.5 mm. The channel box bowing behavior is time dependent and driven by the temperature dependence of the SiC irradiation-induced swelling and the neutron flux/fluence gradients. The bowing behavior gradually recovers during the course of the operating cycle as the swelling of the SiC-SiC material saturates. However, the bending relaxation due to temperature gradients does not fully recover and residual bending remains after the swelling saturates in the entire channel box.

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