{"status":"ok","message-type":"work","message-version":"1.0.0","message":{"indexed":{"date-parts":[[2025,10,10]],"date-time":"2025-10-10T01:22:07Z","timestamp":1760059327905,"version":"build-2065373602"},"reference-count":34,"publisher":"MDPI AG","issue":"11","license":[{"start":{"date-parts":[[2025,6,5]],"date-time":"2025-06-05T00:00:00Z","timestamp":1749081600000},"content-version":"vor","delay-in-days":0,"URL":"https:\/\/creativecommons.org\/licenses\/by\/4.0\/"}],"funder":[{"DOI":"10.13039\/501100001809","name":"National Natural Science Foundation of China","doi-asserted-by":"publisher","award":["12132005"],"award-info":[{"award-number":["12132005"]}],"id":[{"id":"10.13039\/501100001809","id-type":"DOI","asserted-by":"publisher"}]}],"content-domain":{"domain":[],"crossmark-restriction":false},"short-container-title":["Materials"],"abstract":"<jats:p>Nuclear fuel pellets are subject to stress for long periods during the in-pile operation, and this study on high-temperature creep performance is of great significance for predicting the in-pile behaviors and safety evaluation of fuel elements. In the present study, a mixture of ZrC (50 wt%), SiC (46 wt%), and Si (4 wt%) powder was ball-milled for 24 h and then evaporated to obtain ZrC\u2013SiC composite material. ZrC\u2013SiC composite was adopted as the matrix, with ZrO2 surrogate kernel TRSIO particles and dispersion coated particle fuel pellets prepared with different TRISO packing fractions using the Spark Plasma Sintering (SPS) process. This study on compressive creep performances was conducted under a temperature range of 1373\u20132073 K and a stress range of 5\u2013250 MPa, elucidating the creep behavior and mechanism of dispersed coated particles fuel pellets, and obtaining the variation laws of key parameters such as creep stress exponents and activation energy with TRISO packing fraction. The results showed that creep stress exponents of the surrogate fuel pellets are between 0.89 and 2.12. The activation energies for high temperature\u2013low stress creep (1873\u20132073 K, 5\u201350 MPa) are 457.81\u2013623.77 kJ\/mol, and 135.14\u2013161.59 kJ\/mol for low temperature high stress creep (1373\u20131773 K, 50\u2013250 MPa). Based on the experimental results, a high-temperature creep model was established, providing a valuable reference for the research and application of a ceramic matrix dispersed with coated particle fuels.<\/jats:p>","DOI":"10.3390\/ma18112659","type":"journal-article","created":{"date-parts":[[2025,6,5]],"date-time":"2025-06-05T08:34:32Z","timestamp":1749112472000},"page":"2659","update-policy":"https:\/\/doi.org\/10.3390\/mdpi_crossmark_policy","source":"Crossref","is-referenced-by-count":0,"title":["Compressive Creep Performances of Dispersion Coated Particle Surrogate Fuel Pellets with ZrC\u2013SiC Composite Matrix"],"prefix":"10.3390","volume":"18","author":[{"given":"Qisen","family":"Ren","sequence":"first","affiliation":[{"name":"Shenzhen International Graduate School, Tsinghua University, Shenzhen 518055, China"},{"name":"China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518026, China"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Yang","family":"Liu","sequence":"additional","affiliation":[{"name":"China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518026, China"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Runjie","family":"Fang","sequence":"additional","affiliation":[{"name":"China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518026, China"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Lixiang","family":"Wu","sequence":"additional","affiliation":[{"name":"China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518026, China"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Weiqiang","family":"Liu","sequence":"additional","affiliation":[{"name":"Shenzhen International Graduate School, Tsinghua University, Shenzhen 518055, China"}],"role":[{"role":"author","vocabulary":"crossref"}]}],"member":"1968","published-online":{"date-parts":[[2025,6,5]]},"reference":[{"key":"ref_1","doi-asserted-by":"crossref","first-page":"374","DOI":"10.1016\/j.jnucmat.2013.12.005","article-title":"Accident tolerant fuels for LWRs: A perspective","volume":"448","author":"Zinkle","year":"2014","journal-title":"J. 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