TRISO SiC Failure Probability for Reactivity Initiated Accidents in High-Temperature Gas-Cooled Reactors

Ghezzi, Carlotta G.; Kile, Robert F.; Brown, Nicholas R.

doi:10.1080/00295639.2022.2097466

TRISO SiC Failure Probability for Reactivity Initiated Accidents in High-Temperature Gas-Cooled Reactors

Journal Article · Thu Aug 11 00:00:00 EDT 2022 · Nuclear Science and Engineering

DOI:https://doi.org/10.1080/00295639.2022.2097466· OSTI ID:2499449

Ghezzi, Carlotta G. ^[1]; Kile, Robert F. ^[1]; ^[1]

University of Tennessee, Knoxville, TN (United States)

This work analyzes the failure process of the silicon carbide (SiC) layer in tristructural isotropic (TRISO) during reactivity-initiated accident scenarios for a high-temperature gas-cooled reactor (HTGR) with BISON. Two cases are considered—a group control rod withdrawal (CRW) and a control rod ejection (CRE)—reproduced from a previous study. Failure probability is modeled using Weibull statistics, and worst-case scenario Weibull parameters are adopted to simulate the envelopes in BISON with a one-dimensional TRISO model. CRW scenario results are characterized by higher values of maximum energy deposition and final temperature and volumetric strain with respect to the CRE ones, but the latter have remarkably higher SiC failure probability, mainly due to the offset in strain rates between the two cases. This work also confirms the validity and conservatism of the performance envelopes produced in a previous work by replicating the envelope formulation using RELAP5-3D and RAVEN with a different sampling technique and obtaining consistent results. A sensitivity analysis using the Sobol variance decomposition method on SiC failure probability is then performed involving a set of inputs on both CRW and CRE. The two most important parameters are Weibull modulus and characteristic stress, and their relative importance depends on the specific case. The proposed interpretation of the results is that both energy deposition and strain rate influence the relative degree of importance of the failure parameters. Computation of 95% confidence intervals around worst-case scenario SiC failure probability values is also carried out for four different sets of Weibull parameters. Heren a new criterion for SiC TRISO quality classification built upon safety-based ranges of Weibull parameters is proposed to be integrated in future Fuel-Production Quality Assurance Plans.

View Accepted Manuscript (DOE)

Research Organization:: University of Tennessee, Knoxville, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC07-05ID14517; NE0008998

OSTI ID:: 2499449

Alternate ID(s):: OSTI ID: 2424235

Journal Information:: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 11 Vol. 196; ISSN 0029-5639

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

References (36)

On the distribution of points in a cube and the approximate evaluation of integrals Sobol', I. M. USSR Computational Mathematics and Mathematical Physics, Vol. 7, Issue 4 https://doi.org/10.1016/0041-5553(67)90144-9	journal	January 1967
Uniformly distributed sequences with an additional uniform property Sobol, I. M. USSR Computational Mathematics and Mathematical Physics, Vol. 16, Issue 5 https://doi.org/10.1016/0041-5553(76)90154-3	journal	January 1976
MHTGR development in the United States Williams, P. M.; Silady, F. A.; Dunn, T. D. Progress in Nuclear Energy, Vol. 28, Issue 3 https://doi.org/10.1016/0149-1970(94)90002-7	journal	January 1994
Making best use of model evaluations to compute sensitivity indices Saltelli, Andrea Computer Physics Communications, Vol. 145, Issue 2 https://doi.org/10.1016/S0010-4655(02)00280-1	journal	May 2002
Global sensitivity indices for nonlinear mathematical models and their Monte Carlo estimates Sobol′, I. M. Mathematics and Computers in Simulation, Vol. 55, Issue 1-3 https://doi.org/10.1016/S0378-4754(00)00270-6	journal	February 2001
Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics Lu, Cihang; Hiscox, Briana D.; Terrani, Kurt A. Annals of Nuclear Energy, Vol. 114 https://doi.org/10.1016/j.anucene.2017.12.021	journal	April 2018
Variance based sensitivity analysis of model output. Design and estimator for the total sensitivity index Saltelli, Andrea; Annoni, Paola; Azzini, Ivano Computer Physics Communications, Vol. 181, Issue 2 https://doi.org/10.1016/j.cpc.2009.09.018	journal	February 2010
Miniaturized fracture stress tests for thin-walled tubular SiC specimens Byun, T. S.; Lara-Curzio, E.; Lowden, R. A. Journal of Nuclear Materials, Vol. 367-370 https://doi.org/10.1016/j.jnucmat.2007.03.014	journal	August 2007
Handbook of SiC properties for fuel performance modeling Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.016	journal	September 2007
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
Mechanical characteristics of SiC coating layer in TRISO fuel particles Hosemann, P.; Martos, J. N.; Frazer, D. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.08.041	journal	November 2013
Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents Cinbiz, M. Nedim; Koyanagi, Takaaki; Singh, Gyanender Journal of Nuclear Materials, Vol. 514 https://doi.org/10.1016/j.jnucmat.2018.11.023	journal	February 2019
Variance-based sensitivity analysis applied to the hydrogen migration and redistribution model in Bison. Part II: Uncertainty quantification and optimization Aly, Zineb; Casagranda, Albert; Pastore, Giovanni Journal of Nuclear Materials, Vol. 523 https://doi.org/10.1016/j.jnucmat.2019.06.023	journal	September 2019
Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments Aly, Zineb; Casagranda, Albert; Pastore, Giovanni Journal of Nuclear Materials, Vol. 524 https://doi.org/10.1016/j.jnucmat.2019.06.035	journal	October 2019
Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON Schappel, D.; Brown, N. R.; Terrani, K. A. Journal of Nuclear Materials, Vol. 530 https://doi.org/10.1016/j.jnucmat.2019.151965	journal	March 2020
A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications Brown, Nicholas R. Journal of Nuclear Materials, Vol. 534 https://doi.org/10.1016/j.jnucmat.2020.152139	journal	June 2020
Evaluation of the mechanical performance of silicon carbide in TRISO fuel at high temperatures Rohbeck, Nadia; Xiao, Ping Nuclear Engineering and Design, Vol. 306 https://doi.org/10.1016/j.nucengdes.2016.05.040	journal	September 2016
Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process Lu, Cihang; Koyanagi, Takaaki; Katoh, Yutai Nuclear Engineering and Design, Vol. 345 https://doi.org/10.1016/j.nucengdes.2019.02.012	journal	April 2019
Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost Lu, Cihang; Brown, Nicholas R. Nuclear Engineering and Design, Vol. 347 https://doi.org/10.1016/j.nucengdes.2019.03.022	journal	June 2019
Reactor performance and safety characteristics of two-phase composite moderator concepts for modular high temperature gas cooled reactors Duchnowski, Edward M.; Kile, Robert F.; Snead, Lance L. Nuclear Engineering and Design, Vol. 368 https://doi.org/10.1016/j.nucengdes.2020.110824	journal	November 2020
Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor Gorton, Jacob P.; Brown, Nicholas R. Nuclear Engineering and Design, Vol. 370 https://doi.org/10.1016/j.nucengdes.2020.110865	journal	December 2020
Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology Scarlat, Raluca O.; Laufer, Michael R.; Blandford, Edward D. Progress in Nuclear Energy, Vol. 77 https://doi.org/10.1016/j.pnucene.2014.07.002	journal	November 2014
Sensitivity analysis applied to SiC failure probability in TRISO modeled with BISON Ghezzi, Carlotta G.; Schappel, Daniel; Pastore, Giovanni Progress in Nuclear Energy, Vol. 153 https://doi.org/10.1016/j.pnucene.2022.104431	journal	November 2022
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms Williamson, Richard L.; Hales, Jason D.; Novascone, Stephen R. Nuclear Technology https://doi.org/10.1080/00295450.2020.1836940	journal	March 2021
Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions Umeda, Miki; Sugiyama, Tomoyuki; Nagase, Fumihisa Journal of Nuclear Science and Technology, Vol. 47, Issue 11 https://doi.org/10.1080/18811248.2010.9711663	journal	November 2010
Fracture statistics of brittle materials: Weibull or normal distribution Lu, Chunsheng; Danzer, Robert; Fischer, Franz Dieter Physical Review E, Vol. 65, Issue 6 https://doi.org/10.1103/PhysRevE.65.067102	journal	June 2002
Mechanisms Responsible for Strain-Rate-Dependent Compressive Strength in Ceramic Materials Lankford, J. Journal of the American Ceramic Society, Vol. 64, Issue 2 https://doi.org/10.1111/j.1151-2916.1981.tb09570.x	journal	February 1981
Fracture Strength of Plate and Tubular Forms of Monolithic Silicon Carbide Produced by Chemical Vapor Deposition Cockeram, Brian Vern Journal of the American Ceramic Society, Vol. 85, Issue 3 https://doi.org/10.1111/j.1151-2916.2002.tb00139.x	journal	December 2004
Evaluation of the Fracture Strength for Silicon Carbide Layers in the Tri-Isotropic-Coated Fuel Particle Hong, Seong-Gu; Byun, Thak-Sang; Lowden, Richard A. Journal of the American Ceramic Society, Vol. 90, Issue 1 https://doi.org/10.1111/j.1551-2916.2005.01367.x	journal	January 2007
Enterococcus faecalis glutathione reductase: purification, characterization and expression under normal and hyperbaric O2 conditions Patel, Mehul P.; Marcinkeviciene, Jovita; Blanchard, John S. FEMS Microbiology Letters, Vol. 166, Issue 1 https://doi.org/10.1111/j.1574-6968.1998.tb13197.x	journal	September 1998
Evaluation of Fracture Stress for the SiC Layer of TRISO-Coated Fuel Particles Using a Modified Crush Test Method: Evaluation of Fracture Stress for the SiC Layer of TRISO-Coated Fuel Particles Byun, Thak Sang; Hunn, John D.; Miller, James H. International Journal of Applied Ceramic Technology, Vol. 7, Issue 3 https://doi.org/10.1111/j.1744-7402.2009.02462.x	journal	November 2009
Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD/NEA MHTGR-350 Benchmark Strydom, G.; Epiney, A. S.; Alfonsi, A. Nuclear Technology, Vol. 193, Issue 1 https://doi.org/10.13182/NT14-146	journal	January 2016
Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients Cleveland, John Nuclear Technology, Vol. 91, Issue 2 https://doi.org/10.13182/NT90-A34432	journal	August 1990
SALib: An open-source Python library for Sensitivity Analysis Herman, Jon; Usher, Will The Journal of Open Source Software, Vol. 2, Issue 9 https://doi.org/10.21105/joss.00097	journal	January 2017
BISON Theory Manual The Equations behind Nuclear Fuel Analysis Hales, J. D.; Williamson, R. L.; Novascone, S. R. https://doi.org/10.2172/1374503	report	September 2016
Fabrication and Characterization of Sixteen SiC Variants Deposited on the Same IPyC Substrate for Fracture Strength Testing Hunn, John D.; Byun, Thak Sang; Miller, James H. https://doi.org/10.2172/1798589	report	December 2009

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