Compressive Creep Performances of Dispersion Coated Particle Surrogate Fuel Pellets with ZrC–SiC Composite Matrix

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 (4...

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Published inMaterials Vol. 18; no. 11; p. 2659
Main Authors Ren, Qisen, Liu, Yang, Fang, Runjie, Wu, Lixiang, Liu, Weiqiang
Format Journal Article
LanguageEnglish
Published Switzerland MDPI AG 05.06.2025
MDPI
Subjects
Activation energy
Carbon
Coated particles
Cold flow
Composite materials
Creep (materials)
Design optimization
Exponents
Heat conductivity
High temperature
Hot pressing
Low temperature
Nuclear accidents & safety
Nuclear energy
Nuclear fuel elements
Nuclear fuels
Nuclear industry
Nuclear power plants
Nuclear reactors
Nuclear safety
Oxidation
Pellets
Plasma sintering
Polyvinyl alcohol
Powders
Silicon carbide
Sintering
Sintering (powder metallurgy)
Spark plasma sintering
Temperature
Zirconium carbide
Zirconium dioxide
activation energy
creep
stress exponent
accident tolerant fuel
dispersion coated particle fuel
Online AccessGet full text
ISSN1996-1944
1996-1944
DOI10.3390/ma18112659

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Abstract 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–SiC composite material. ZrC–SiC 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 1373–2073 K and a stress range of 5–250 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–low stress creep (1873–2073 K, 5–50 MPa) are 457.81–623.77 kJ/mol, and 135.14–161.59 kJ/mol for low temperature high stress creep (1373–1773 K, 50–250 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.
AbstractList 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–SiC composite material. ZrC–SiC composite was adopted as the matrix, with ZrO 2 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 1373–2073 K and a stress range of 5–250 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–low stress creep (1873–2073 K, 5–50 MPa) are 457.81–623.77 kJ/mol, and 135.14–161.59 kJ/mol for low temperature high stress creep (1373–1773 K, 50–250 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.
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-SiC composite material. ZrC-SiC 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 1373-2073 K and a stress range of 5-250 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-low stress creep (1873-2073 K, 5-50 MPa) are 457.81-623.77 kJ/mol, and 135.14-161.59 kJ/mol for low temperature high stress creep (1373-1773 K, 50-250 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.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-SiC composite material. ZrC-SiC 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 1373-2073 K and a stress range of 5-250 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-low stress creep (1873-2073 K, 5-50 MPa) are 457.81-623.77 kJ/mol, and 135.14-161.59 kJ/mol for low temperature high stress creep (1373-1773 K, 50-250 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.
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–SiC composite material. ZrC–SiC composite was adopted as the matrix, with ZrO[sub.2] 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 1373–2073 K and a stress range of 5–250 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–low stress creep (1873–2073 K, 5–50 MPa) are 457.81–623.77 kJ/mol, and 135.14–161.59 kJ/mol for low temperature high stress creep (1373–1773 K, 50–250 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.
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–SiC composite material. ZrC–SiC 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 1373–2073 K and a stress range of 5–250 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–low stress creep (1873–2073 K, 5–50 MPa) are 457.81–623.77 kJ/mol, and 135.14–161.59 kJ/mol for low temperature high stress creep (1373–1773 K, 50–250 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.
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-SiC composite material. ZrC-SiC composite was adopted as the matrix, with ZrO 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 1373-2073 K and a stress range of 5-250 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-low stress creep (1873-2073 K, 5-50 MPa) are 457.81-623.77 kJ/mol, and 135.14-161.59 kJ/mol for low temperature high stress creep (1373-1773 K, 50-250 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.
Audience Academic
Author Liu, Yang
Liu, Weiqiang
Fang, Runjie
Ren, Qisen
Wu, Lixiang
AuthorAffiliation 1 Shenzhen International Graduate School, Tsinghua University, Shenzhen 518055, China; liuweiqiang@mail.tsinghua.edu.cn
2 China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518026, China; liuyang@cgnpc.com.cn (Y.L.); fangrunjie@cgnpc.com.cn (R.F.); wulixiang@cgnpc.com.cn (L.W.)
AuthorAffiliation_xml – name: 2 China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518026, China; liuyang@cgnpc.com.cn (Y.L.); fangrunjie@cgnpc.com.cn (R.F.); wulixiang@cgnpc.com.cn (L.W.)
– name: 1 Shenzhen International Graduate School, Tsinghua University, Shenzhen 518055, China; liuweiqiang@mail.tsinghua.edu.cn
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Issue 11
Keywords activation energy
creep
stress exponent
accident tolerant fuel
dispersion coated particle fuel
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Snippet 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...
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StartPage 2659
SubjectTerms Activation energy
Carbon
Coated particles
Cold flow
Composite materials
Creep (materials)
Design optimization
Exponents
Heat conductivity
High temperature
Hot pressing
Low temperature
Nuclear accidents & safety
Nuclear energy
Nuclear fuel elements
Nuclear fuels
Nuclear industry
Nuclear power plants
Nuclear reactors
Nuclear safety
Oxidation
Pellets
Plasma sintering
Polyvinyl alcohol
Powders
Silicon carbide
Sintering
Sintering (powder metallurgy)
Spark plasma sintering
Temperature
Zirconium carbide
Zirconium dioxide
Title Compressive Creep Performances of Dispersion Coated Particle Surrogate Fuel Pellets with ZrC–SiC Composite Matrix
URI https://www.ncbi.nlm.nih.gov/pubmed/40508655
https://www.proquest.com/docview/3217738958
https://www.proquest.com/docview/3218473272
https://pubmed.ncbi.nlm.nih.gov/PMC12156877
Volume 18
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