X-ray tomography study on the crushing strength and irradiation behaviour of dedicated tristructural isotropic nuclear fuel particles at 1000 °C

Liu, Dong; Knol, Steven; Ell, Jon; Barnard, Harold; Davies, Mark; Vreeling, Jan A.; Ritchie, Robert O.

doi:10.1016/j.matdes.2019.108382

Title: X-ray tomography study on the crushing strength and irradiation behaviour of dedicated tristructural isotropic nuclear fuel particles at 1000 °C

Journal Article · Sat Feb 01 00:00:00 EST 2020 · Materials & Design

DOI:https://doi.org/10.1016/j.matdes.2019.108382· OSTI ID:1995585

; Knol, Steven; Ell, Jon; Barnard, Harold; Davies, Mark; Vreeling, Jan A.; Ritchie, Robert O.

Two types of dedicated Tristructural isotropic (TRISO) nuclear fuel particles, PyC-1 (Kernel/Buffer/PyC) and PyC-2 (Kernel/Buffer/SiC/PyC) from PYCASSO (Pyrocarbon irradiation for creep and swelling/shrinkage of objects) neutron irradiation experiments, were studied. For unirradiated particles, crushing experiments using a unique hot cell, combined with in situ X-ray computed micro-tomography (XCT) imaging, were conducted at room temperature (RT) and at 1000 °C. Although the SiC layer on the particles is presumed to provide ‘mechanical stability’ to the TRISO particles, results showed a remarkable reduction (~45%) in the crushing strength of the PyC-2 particles at 1000 °C compared to RT. The fracture patterns of the two types of particles, both at the contact zone and on subsequent propagation, differ significantly at RT and 1000 °C. Further, irradiated particles (irradiation temperature: 1000 ± 20 °C; irradiation doses: 1.08–1.23 dpa and 1.49–1.51 dpa) were imaged by XCT; 250 PyC-1 particles and 223 PyC-2 particles were studied in total and the change in radius/layer thickness in each type was examined. It was found that the buffer densification was lower in PyC-1 particles compared to PyC-2 particles, and the PyC layer shrank in the PyC-I particles, whereas it expanded in PyC-2. Results are discussed in terms of how the residual stresses can impact the high-temperature and post-irradiation behavior of these particles.

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Research Organization:: Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). Advanced Light Source (ALS)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES); Engineering and Physical Sciences Resource Council (EPSRC)

Grant/Contract Number:: AC02-05CH11231; EP/N004493/1

OSTI ID:: 1995585

Alternate ID(s):: OSTI ID: 1760216

Journal Information:: Materials & Design, Journal Name: Materials & Design Vol. 187 Journal Issue: C; ISSN 0264-1275

Publisher:: ElsevierCopyright Statement

Country of Publication:: United Kingdom

Language:: English

References (55)

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
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
Real-time quantitative imaging of failure events in materials under load at temperatures above 1,600 °C Bale, Hrishikesh A.; Haboub, Abdel; MacDowell, Alastair A. Nature Materials, Vol. 12, Issue 1 https://doi.org/10.1038/nmat3497	journal	December 2012
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
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
Dimensional change, irradiation creep and thermal/mechanical property changes in nuclear graphite Marsden, B. J.; Haverty, M.; Bodel, W. International Materials Reviews, Vol. 61, Issue 3 https://doi.org/10.1080/09506608.2015.1136460	journal	April 2016
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
A technique for measuring the strength of high temperature reactor fuel particle coatings Gilchrist, K. E.; Brocklehurst, J. E. Journal of Nuclear Materials, Vol. 43, Issue 3 https://doi.org/10.1016/0022-3115(72)90069-4	journal	June 1972
Microencapsulated fuel technology for commercial light water and advanced reactor application Terrani, Kurt A.; Snead, Lance L.; Gehin, Jess C. Journal of Nuclear Materials, Vol. 427, Issue 1-3, p. 209-224 https://doi.org/10.1016/j.jnucmat.2012.05.021	journal	August 2012
In-situ nanoindentation of irradiated silicon carbide in TRISO particle fuel up to 500 °C Rohbeck, Nadia; Tsivoulas, Dimitrios; Shapiro, Ian P. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.035	journal	October 2015
HTR fuel coating separate effect test PYCASSO de Groot, Sander; Guillermier, Pierre; Sawa, Kazuhiro Nuclear Engineering and Design, Vol. 240, Issue 10 https://doi.org/10.1016/j.nucengdes.2010.05.052	journal	October 2010
Crushing behaviour of high temperature reactor coated fuel particles Briggs, A.; Davidge, R. W.; Padgett, C. Journal of Nuclear Materials, Vol. 61, Issue 3 https://doi.org/10.1016/0022-3115(76)90262-2	journal	September 1976
A control approach investigation of the Xe-100 plant to perform load following within the operational range of 100 – 25 – 100% Brits, Yvotte; Botha, Frikkie; van Antwerpen, Herman Nuclear Engineering and Design, Vol. 329 https://doi.org/10.1016/j.nucengdes.2017.11.041	journal	April 2018
Tensile testing of materials at high temperatures above 1700 °C with in situ synchrotron X-ray micro-tomography Haboub, Abdel; Bale, Hrishikesh A.; Nasiatka, James R. Review of Scientific Instruments, Vol. 85, Issue 8 https://doi.org/10.1063/1.4892437	journal	August 2014
Evaluation of the Mechanical Properties of TRISO Particles Using Nanoindentation and Ring Compression Testing Frazer, D.; Szornel, J.; Krumwiede, D. L. Experimental Mechanics, Vol. 57, Issue 7 https://doi.org/10.1007/s11340-017-0277-z	journal	April 2017
Research and Development of HTTR Coated Particle Fuel Fukuda, Kousku; Ogaw, Toru; Hayashi, Kimio Journal of Nuclear Science and Technology, Vol. 28, Issue 6 https://doi.org/10.1080/18811248.1991.9731396	journal	June 1991
Thermal expansion coefficient of alumina films developed by oxidation of a FeCrAl alloy determined by a deflection technique Huntz, A. M.; Maréchal, L.; Lesage, B. Applied Surface Science, Vol. 252, Issue 22 https://doi.org/10.1016/j.apsusc.2005.08.116	journal	September 2006
The DOE advanced gas reactor fuel development and qualification program Petti, David; Maki, John; Hunn, John JOM, Vol. 62, Issue 9 https://doi.org/10.1007/s11837-010-0140-5	journal	September 2010
The first irradiation testing and PIE or TRISO-coated particle fuel in Korea Kim, Bong Goo; Yeo, Sunghwan; Jeong, Kyung-Chai Nuclear Engineering and Design, Vol. 329 https://doi.org/10.1016/j.nucengdes.2018.01.037	journal	April 2018
PYCASSO: X-ray tomography on HTR coated particles Knol, S.; Hania, P. R.; Janssen, B. Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.11.033	journal	May 2014
A review of TRISO-coated particle nuclear fuel performance models Liu, B.; Liang, T.; Tang, C. Rare Metals, Vol. 25, Issue 6 https://doi.org/10.1016/S1001-0521(07)60101-6	journal	October 2006
Coated particle fuel to improve safety, design, economics in water-cooled and gas-cooled reactors Porta, J.; Lo Pinto, P.; Bonnet, M. Progress in Nuclear Energy, Vol. 38, Issue 3-4 https://doi.org/10.1016/S0149-1970(00)00146-3	journal	January 2001
High temperature fast-neutron irradiation of pyrolytic-carbon-coated ThO2 microspheres Hewette, D. M. Carbon, Vol. 7, Issue 3 https://doi.org/10.1016/0008-6223(69)90125-0	journal	June 1969
Performance of Pyrolytic Carbon-Coated Uranium Oxide Particles During Irradiation at High Temperature Reagan, P. E.; Beatty, R. L.; Long, E. L. Nuclear Science and Engineering, Vol. 28, Issue 1 https://doi.org/10.13182/NSE67-A18664	journal	April 1967
A review of the Brazilian test for rock tensile strength determination. Part I: calculation formula Andreev, G. E. Mining Science and Technology, Vol. 13, Issue 3 https://doi.org/10.1016/0167-9031(91)91006-4	journal	December 1991
Elastic contact between randomly rough surfaces: Comparison of theory with numerical results Persson, B. N. J.; Bucher, F.; Chiaia, B. Physical Review B, Vol. 65, Issue 18 https://doi.org/10.1103/PhysRevB.65.184106	journal	April 2002
Irradiation behavior of isotropic carbons Bokros, J. C.; Stevens, D. W. Carbon, Vol. 9, Issue 1 https://doi.org/10.1016/0008-6223(71)90141-2	journal	January 1971
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
Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance Petti, D. A.; Buongiorno, J.; Maki, J. T. Nuclear Engineering and Design, Vol. 222, Issue 2-3 https://doi.org/10.1016/S0029-5493(03)00033-5	journal	June 2003
Results of the HFR-EU1 fuel irradiation of INET and AVR pebbles in the HFR Petten Laurie, Mathias; Marmier, Alain; Berg, Gerard Nuclear Engineering and Design, Vol. 251 https://doi.org/10.1016/j.nucengdes.2011.10.063	journal	October 2012
The fracture strength of TRISO-coated particles determined by compression testing between soft aluminium anvils van Rooyen, Gerrit T.; Preez, Rudy du; Villiers, Johan de Journal of Nuclear Materials, Vol. 403, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.06.011	journal	August 2010
Fracture strength and principal stress fields during crush testing of the SiC layer in TRISO-coated fuel particles Davis, Brian C.; Ward, Logan; Butt, Darryl P. Journal of Nuclear Materials, Vol. 477 https://doi.org/10.1016/j.jnucmat.2016.05.018	journal	August 2016
The influence of annealing temperature on the strength of TRISO coated particles van Rooyen, I. J.; Neethling, J. H.; van Rooyen, P. M. Journal of Nuclear Materials, Vol. 402, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2010.05.009	journal	July 2010
Crushing strengths of SiC-Triso and ZrC-Triso coated fuel particles Ogawa, T.; Ikawa, K. Journal of Nuclear Materials, Vol. 98, Issue 1-2 https://doi.org/10.1016/0022-3115(81)90383-4	journal	May 1981
Nano-cracks in a synthetic graphite composite for nuclear applications Liu, Dong; Cherns, David Philosophical Magazine, Vol. 98, Issue 14 https://doi.org/10.1080/14786435.2018.1433886	journal	February 2018
Fabrication and characterization of fully ceramic microencapsulated fuels Terrani, K. A.; Kiggans, J. O.; Katoh, Y. Journal of Nuclear Materials, Vol. 426, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.03.049	journal	July 2012
Crush strength of silicon carbide coated TRISO particles: Influence of test method and process variables Cromarty, R. D.; van Rooyen, G. T.; de Villiers, J. P. R. Journal of Nuclear Materials, Vol. 445, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.041	journal	February 2014
Irradiation Device for Irradiation Testing of Coated Particle fuel at Hanaro Kim, Bong Goo; Park, Sung Jae; Hong, Sung Taek Nuclear Engineering and Technology, Vol. 45, Issue 7 https://doi.org/10.5516/NET.07.2013.045	journal	December 2013
Crushing strength of irradiated Triso coated fuel particles Minato, Kazuo; Fukuda, Kousaku; Ikawa, Katsuichi Journal of Nuclear Materials, Vol. 119, Issue 2-3 https://doi.org/10.1016/0022-3115(83)90211-8	journal	December 1983
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
The microstructure, coefficient of thermal expansion and flexural strength of cordierite ceramics prepared from alumina with different particle sizes Kuscer, Danjela; Bantan, Ines; Hrovat, Marko Journal of the European Ceramic Society, Vol. 37, Issue 2 https://doi.org/10.1016/j.jeurceramsoc.2016.08.032	journal	February 2017
The development of HTGR-TRISO coated fuels in the globe: challenging of Indonesia to be an HTGR fuel producer Taryo, T.; Husnayani, I.; Subekti, Rm Journal of Physics: Conference Series, Vol. 1198, Issue 2 https://doi.org/10.1088/1742-6596/1198/2/022062	journal	April 2019
Crushing Strength of High-Temperature Gas-Cooled Reactor Fuel Particles Lackey, W. J.; Stinton, D. P.; Davis, L. E. Nuclear Technology, Vol. 31, Issue 2 https://doi.org/10.13182/NT76-A31682	journal	November 1976
Irradiation performance of AGR-1 high temperature reactor fuel Demkowicz, Paul A.; Hunn, John D.; Ploger, Scott A. Nuclear Engineering and Design, Vol. 306 https://doi.org/10.1016/j.nucengdes.2015.09.011	journal	September 2016
Microstructural analysis of TRISO particles using multi-scale X-ray computed tomography Lowe, T.; Bradley, R. S.; Yue, S. Journal of Nuclear Materials, Vol. 461 https://doi.org/10.1016/j.jnucmat.2015.02.034	journal	June 2015
Hoop tensile strength testing of small diameter ceramic particles Wereszczak, A. A.; Jadaan, O. M.; Lin, H. -T. Journal of Nuclear Materials, Vol. 361, Issue 1 https://doi.org/10.1016/j.jnucmat.2006.11.013	journal	March 2007
PYCASSO: Irradiation of HTR coated particles at high temperatures Knol, S.; de Groot, S.; Hania, P. R. Nuclear Engineering and Design, Vol. 251 https://doi.org/10.1016/j.nucengdes.2011.10.050	journal	October 2012
The elastic contact of a rough surface Bush, A. W.; Gibson, R. D.; Thomas, T. R. Wear, Vol. 35, Issue 1 https://doi.org/10.1016/0043-1648(75)90145-3	journal	November 1975
Three Design Basis Accidents’ Analysis on the HTR-10GT Lang, Minggang; Xie, Heng; Dong, Yujie Science and Technology of Nuclear Installations, Vol. 2017 https://doi.org/10.1155/2017/1686291	journal	January 2017
Long time experience with the development of HTR fuel elements in Germany Nickel, H.; Nabielek, H.; Pott, G. Nuclear Engineering and Design, Vol. 217, Issue 1-2 https://doi.org/10.1016/S0029-5493(02)00128-0	journal	August 2002
Measurement of kernel swelling and buffer densification in irradiated UCO-TRISO particles Bower, Gordon R.; Ploger, Scott A.; Demkowicz, Paul A. Journal of Nuclear Materials, Vol. 486 https://doi.org/10.1016/j.jnucmat.2017.01.006	journal	April 2017
Strength Measurement of Ceramic Spheres Using a Diametrally Compressed "C-Sphere" Specimen Wereszczak, Andrew A.; Kirkland, Timothy P.; Jadaan, Osama M. Journal of the American Ceramic Society, Vol. 90, Issue 6 https://doi.org/10.1111/j.1551-2916.2007.01639.x	journal	June 2007
Analysis on the post-irradiation examination of the HANARO miniplate-1 irradiation test for kijang research reactor Park, Jong Man; Tahk, Young Wook; Jeong, Yong Jin Nuclear Engineering and Technology, Vol. 49, Issue 5 https://doi.org/10.1016/j.net.2017.04.003	journal	August 2017
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
Evaluation of thermal conductivity of the constituent layers in TRISO particles using Raman spectroscopy Cao, Fangcheng; Liu, Bing; Wang, Xin Journal of the European Ceramic Society, Vol. 37, Issue 15 https://doi.org/10.1016/j.jeurceramsoc.2017.07.008	journal	December 2017

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Title: X-ray tomography study on the crushing strength and irradiation behaviour of dedicated tristructural isotropic nuclear fuel particles at 1000 °C

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