Penghui Lei , Xiaoyu Ji , Jiahao Chen , Yonghong Lu , Jie Qiu , Di Yun
{"title":"(HfNbZrTaW)C5高熵碳化物陶瓷火花等离子烧结用作乏燃料屏蔽材料","authors":"Penghui Lei , Xiaoyu Ji , Jiahao Chen , Yonghong Lu , Jie Qiu , Di Yun","doi":"10.1016/j.vacuum.2025.114096","DOIUrl":null,"url":null,"abstract":"<div><div>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)C<sub>5</sub> 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)C<sub>5</sub> 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 % ZrB<sub>2</sub> into (HfNbZrTaW)C<sub>5</sub> 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.</div></div>","PeriodicalId":23559,"journal":{"name":"Vacuum","volume":"234 ","pages":"Article 114096"},"PeriodicalIF":3.9000,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"(HfNbZrTaW)C5 high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels\",\"authors\":\"Penghui Lei , Xiaoyu Ji , Jiahao Chen , Yonghong Lu , Jie Qiu , Di Yun\",\"doi\":\"10.1016/j.vacuum.2025.114096\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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)C<sub>5</sub> 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)C<sub>5</sub> 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 % ZrB<sub>2</sub> into (HfNbZrTaW)C<sub>5</sub> 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.</div></div>\",\"PeriodicalId\":23559,\"journal\":{\"name\":\"Vacuum\",\"volume\":\"234 \",\"pages\":\"Article 114096\"},\"PeriodicalIF\":3.9000,\"publicationDate\":\"2025-04-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Vacuum\",\"FirstCategoryId\":\"88\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0042207X25000867\",\"RegionNum\":2,\"RegionCategory\":\"材料科学\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"2025/1/29 0:00:00\",\"PubModel\":\"Epub\",\"JCR\":\"Q2\",\"JCRName\":\"MATERIALS SCIENCE, MULTIDISCIPLINARY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Vacuum","FirstCategoryId":"88","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0042207X25000867","RegionNum":2,"RegionCategory":"材料科学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/1/29 0:00:00","PubModel":"Epub","JCR":"Q2","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
(HfNbZrTaW)C5 high entropy carbide ceramics by spark plasma sintering for shielding materials of spent fuels
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.
期刊介绍:
Vacuum is an international rapid publications journal with a focus on short communication. All papers are peer-reviewed, with the review process for short communication geared towards very fast turnaround times. The journal also published full research papers, thematic issues and selected papers from leading conferences.
A report in Vacuum should represent a major advance in an area that involves a controlled environment at pressures of one atmosphere or below.
The scope of the journal includes:
1. Vacuum; original developments in vacuum pumping and instrumentation, vacuum measurement, vacuum gas dynamics, gas-surface interactions, surface treatment for UHV applications and low outgassing, vacuum melting, sintering, and vacuum metrology. Technology and solutions for large-scale facilities (e.g., particle accelerators and fusion devices). New instrumentation ( e.g., detectors and electron microscopes).
2. Plasma science; advances in PVD, CVD, plasma-assisted CVD, ion sources, deposition processes and analysis.
3. Surface science; surface engineering, surface chemistry, surface analysis, crystal growth, ion-surface interactions and etching, nanometer-scale processing, surface modification.
4. Materials science; novel functional or structural materials. Metals, ceramics, and polymers. Experiments, simulations, and modelling for understanding structure-property relationships. Thin films and coatings. Nanostructures and ion implantation.