Modeling Interface Debonding in Coated Fuel Particles with BISON

Schappel, Daniel; Pastore, Giovanni; Terrani, Kurt A.

doi:10.1080/00295639.2021.1955590

Title: Modeling Interface Debonding in Coated Fuel Particles with BISON

Journal Article · 24 August 2021 · Nuclear Science and Engineering

DOI: https://doi.org/10.1080/00295639.2021.1955590 · OSTI ID:1818749

Schappel, Daniel ^[1]; Pastore, Giovanni ^[2];

^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Tennessee, Knoxville, TN (United States)

Here we introduce a meshed debonding model intended for use with tristructural isotropic (TRISO) fuel particles. The ability to better examine the potential effects of interface debonding between the coating layers will enable a host of investigations of the stress state when complex loading and interactions between coated fuel particles are taking place. In this work, the debonding model is discussed in detail. Then, simulations are presented to show the capabilities and limitations of the model. First, a traditional high-temperature gas reactor TRISO particle is considered. Then, a TRISO particle in a graphitic matrix is analyzed, followed by a TRISO particle in a silicon carbide matrix.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1818749

Journal Information:: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 3 Vol. 196; ISSN 0029-5639

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

References (17)

Ceramic coated particle nuclear fuels Dayton, R. W.; Oxley, J. H.; Townley, C. W. Journal of Nuclear Materials, Vol. 11, Issue 1 https://doi.org/10.1016/0022-3115(64)90117-5	journal	January 1964
Fission-product release during postirradiation annealing of several types of coated fuel particles Bullock, R. E. Journal of Nuclear Materials, Vol. 125, Issue 3 https://doi.org/10.1016/0022-3115(84)90558-0	journal	August 1984
The early history of high-temperature helium gas-cooled nuclear power reactors Simnad, Massoud T. Energy, Vol. 16, Issue 1-2 https://doi.org/10.1016/0360-5442(91)90084-Y	journal	January 1991
Shear properties at the PyC/SiC interface of a TRISO-coating Nozawa, T.; Snead, L. L.; Katoh, Y. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.015	journal	September 2007
Calculating failure probabilities for TRISO-coated fuel particles using an integral formulation Miller, Gregory K.; Maki, John T.; Knudson, Darrell L. Journal of Nuclear Materials, Vol. 399, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2010.01.012	journal	April 2010
Multidimensional multiphysics simulation of nuclear fuel behavior Williamson, R. L.; Hales, J. D.; Novascone, S. R. Journal of Nuclear Materials, Vol. 423, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.01.012	journal	April 2012
Microstructure of TRISO coated particles from the AGR-1 experiment: SiC grain size and grain boundary character Kirchhofer, Rita; Hunn, John D.; Demkowicz, Paul A. Journal of Nuclear Materials, Vol. 432, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.08.052	journal	January 2013
Testing of HTR UO2 TRISO fuels in AVR and in material test reactors Kania, Michael J.; Nabielek, Heinz; Verfondern, Karl Journal of Nuclear Materials, Vol. 441, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.05.062	journal	October 2013
Multidimensional multiphysics simulation of TRISO particle fuel Hales, J. D.; Williamson, R. L.; Novascone, S. R. Journal of Nuclear Materials, Vol. 443, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.070	journal	November 2013
Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form Terrani, K. A.; Kiggans, J. O.; Silva, C. M. Journal of Nuclear Materials, Vol. 457 https://doi.org/10.1016/j.jnucmat.2014.10.034	journal	February 2015
Coated particle fuel: Historical perspectives and current progress Demkowicz, Paul A.; Liu, Bing; Hunn, John D. Journal of Nuclear Materials, Vol. 515 https://doi.org/10.1016/j.jnucmat.2018.09.044	journal	March 2019
Uranium nitride tristructural-isotropic fuel particle Terrani, Kurt A.; Jolly, Brian C.; Harp, Jason M. Journal of Nuclear Materials, Vol. 531 https://doi.org/10.1016/j.jnucmat.2020.152034	journal	April 2020
Microscopic analysis of irradiated AGR-1 coated particle fuel compacts Ploger, Scott A.; Demkowicz, Paul A.; Hunn, John D. Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.11.036	journal	May 2014
Detection and analysis of particles with failed SiC in AGR-1 fuel compacts Hunn, John D.; Baldwin, Charles A.; Gerczak, Tyler J. Nuclear Engineering and Design, Vol. 306 https://doi.org/10.1016/j.nucengdes.2015.12.011	journal	September 2016
Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel Demkowicz, Paul A.; Hunn, John D.; Petti, David A. Nuclear Engineering and Design, Vol. 329 https://doi.org/10.1016/j.nucengdes.2017.09.005	journal	April 2018
Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON Schappel, D.; Terrani, K.; Powers, J. J. Nuclear Engineering and Design, Vol. 335 https://doi.org/10.1016/j.nucengdes.2018.05.018	journal	August 2018
Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors Minato, Kazuo; Ogawa, Toru; Sawa, Kazuhiro Nuclear Technology, Vol. 130, Issue 3 https://doi.org/10.13182/NT00-A3093	journal	June 2000

Similar Records

Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another

Journal Article · 2022 · Nuclear Science and Engineering · OSTI ID:1883832

Schappel, Daniel; Terrani, Kurt A.

Evaluation of XCT for Matrix Density Measurement of Particle Fuel Forms

Technical Report · 2024 · OSTI ID:2438889

Helmreich, Grant W.; Montoya, Katherine I.; Hunn, John D.

Two decades of DOE investment lays the foundation for TRISO-fueled reactors

Journal Article · 2020 · Nuclear News · OSTI ID:1659600

Demkowicz, Paul; Hunn, John D.

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
TRISO
debonding
silicon carbide pyrolytic carbon

Title: Modeling Interface Debonding in Coated Fuel Particles with BISON

Citation Formats

References (17)

Similar Records

Related Subjects