(HfNbZrTaW)C5 high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels

Penghui Lei; Xiaoyu Ji; Jiahao Chen; Yonghong Lu; Jie Qiu; Di Yun

doi:10.1016/j.vacuum.2025.114096

(HfNbZrTaW)C₅ high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels

Penghui Lei
, Xiaoyu Ji
, Jiahao Chen
, Yonghong Lu
, Jie Qiu
, Di Yun

School of Energy and Power Engineering

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

For the transportation and storage of spent fuels, where significant levels of neutron and gamma radiation are encountered, shielding materials are essential. In this paper, a new type of (HfNbZrTaW)C₅ high-entropy carbide ceramics with face-centered cubic rock-salt structure was designed and prepared as an integrated shielding material for both neutron and gamma ray protection, intended to replace the existing lead and epoxy resin. A single-phase (HfNbZrTaW)C₅ pellet with the best oxidation resistance was synthesized at 1700 °C by spark plasma sintering (SPS), achieving a theoretical density of 98.51 % and a hardness value of 25.28 GPa. Incorporating 10 wt % ZrB₂ into (HfNbZrTaW)C₅ ceramic sintered at 1700 °C can significantly enhance its the neutron absorption capacity, thermal conductivity, and oxidation resistance, positioning it as a potential integrated shielding material for spent nuclear fuels.

Original language	English
Article number	114096
Journal	Vacuum
Volume	234
DOIs	https://doi.org/10.1016/j.vacuum.2025.114096
State	Published - Apr 2025

Keywords

High-entropy carbide ceramics
Oxidation resistance
Shielding materials
Thermal conductivity

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10.1016/j.vacuum.2025.114096

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@article{961841056a5442839978ae8cd018c5ef,

title = "(HfNbZrTaW)C5 high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels",

abstract = "For the transportation and storage of spent fuels, where significant levels of neutron and gamma radiation are encountered, shielding materials are essential. In this paper, a new type of (HfNbZrTaW)C5 high-entropy carbide ceramics with face-centered cubic rock-salt structure was designed and prepared as an integrated shielding material for both neutron and gamma ray protection, intended to replace the existing lead and epoxy resin. A single-phase (HfNbZrTaW)C5 pellet with the best oxidation resistance was synthesized at 1700 °C by spark plasma sintering (SPS), achieving a theoretical density of 98.51 \% and a hardness value of 25.28 GPa. Incorporating 10 wt \% ZrB2 into (HfNbZrTaW)C5 ceramic sintered at 1700 °C can significantly enhance its the neutron absorption capacity, thermal conductivity, and oxidation resistance, positioning it as a potential integrated shielding material for spent nuclear fuels.",

keywords = "High-entropy carbide ceramics, Oxidation resistance, Shielding materials, Thermal conductivity",

author = "Penghui Lei and Xiaoyu Ji and Jiahao Chen and Yonghong Lu and Jie Qiu and Di Yun",

note = "Publisher Copyright: {\textcopyright} 2025 Elsevier Ltd",

year = "2025",

month = apr,

doi = "10.1016/j.vacuum.2025.114096",

language = "英语",

volume = "234",

journal = "Vacuum",

issn = "0042-207X",

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TY - JOUR

T1 - (HfNbZrTaW)C5 high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels

AU - Lei, Penghui

AU - Ji, Xiaoyu

AU - Chen, Jiahao

AU - Lu, Yonghong

AU - Qiu, Jie

AU - Yun, Di

PY - 2025/4

Y1 - 2025/4

N2 - For the transportation and storage of spent fuels, where significant levels of neutron and gamma radiation are encountered, shielding materials are essential. In this paper, a new type of (HfNbZrTaW)C5 high-entropy carbide ceramics with face-centered cubic rock-salt structure was designed and prepared as an integrated shielding material for both neutron and gamma ray protection, intended to replace the existing lead and epoxy resin. A single-phase (HfNbZrTaW)C5 pellet with the best oxidation resistance was synthesized at 1700 °C by spark plasma sintering (SPS), achieving a theoretical density of 98.51 % and a hardness value of 25.28 GPa. Incorporating 10 wt % ZrB2 into (HfNbZrTaW)C5 ceramic sintered at 1700 °C can significantly enhance its the neutron absorption capacity, thermal conductivity, and oxidation resistance, positioning it as a potential integrated shielding material for spent nuclear fuels.

AB - For the transportation and storage of spent fuels, where significant levels of neutron and gamma radiation are encountered, shielding materials are essential. In this paper, a new type of (HfNbZrTaW)C5 high-entropy carbide ceramics with face-centered cubic rock-salt structure was designed and prepared as an integrated shielding material for both neutron and gamma ray protection, intended to replace the existing lead and epoxy resin. A single-phase (HfNbZrTaW)C5 pellet with the best oxidation resistance was synthesized at 1700 °C by spark plasma sintering (SPS), achieving a theoretical density of 98.51 % and a hardness value of 25.28 GPa. Incorporating 10 wt % ZrB2 into (HfNbZrTaW)C5 ceramic sintered at 1700 °C can significantly enhance its the neutron absorption capacity, thermal conductivity, and oxidation resistance, positioning it as a potential integrated shielding material for spent nuclear fuels.

KW - High-entropy carbide ceramics

KW - Oxidation resistance

KW - Shielding materials

KW - Thermal conductivity

UR - https://www.scopus.com/pages/publications/85216505973

U2 - 10.1016/j.vacuum.2025.114096

DO - 10.1016/j.vacuum.2025.114096

M3 - 文章

AN - SCOPUS:85216505973

SN - 0042-207X

VL - 234

JO - Vacuum

JF - Vacuum

M1 - 114096

ER -

(HfNbZrTaW)C₅ high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels

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Keywords

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