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FUNaK(氟化钠-氟化钾-氟化铀)共晶的热物理性质。

Thermophysical Properties of FUNaK (NaF-KF-UF) Eutectics.

作者信息

Fache Maxime, Voigt Laura, Colle Jean-Yves, Hald John, Beneš Ondřej

机构信息

European Commission, Joint Research Centre (JRC), 76125 Karlsruhe, Germany.

DTU Construct, Technical University of Denmark, 2800 Kongens Lyngby, Denmark.

出版信息

Materials (Basel). 2024 Jun 6;17(11):2776. doi: 10.3390/ma17112776.

DOI:10.3390/ma17112776
PMID:38894038
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC11173649/
Abstract

General interest in the deployment of molten salt reactors (MSRs) is growing, while the available data on uranium-containing fuel salt candidates remains scarce. Thermophysical data are one of the key parameters for reactor design and understanding reactor operability. Hence, filling in the gap of the missing data is crucial to allow for the advancement of MSRs. This study provides novel data for two eutectic compositions within the NaF-KF-UF ternary system which serve as potential fuel candidates for MSRs. Experimental measurements include their melting point, density, fusion enthalpy, and vapor pressure. Additionally, their boiling point was extrapolated from the vapor pressure data, which were, at the same time, used to determine the enthalpy of vaporization. The obtained thermodynamic values were compared with available data from the literature but also with results from thermochemical equilibrium calculations using the JRCMSD database, finding a good correlation, which thus contributed to database validation. Preliminary thoughts on fluoride salt reactor operability based on the obtained results are discussed in this study.

摘要

人们对熔盐反应堆(MSR)部署的普遍兴趣正在增加,而关于含铀燃料盐候选物的现有数据仍然稀少。热物理数据是反应堆设计和理解反应堆可操作性的关键参数之一。因此,填补缺失数据的空白对于推进熔盐反应堆至关重要。本研究提供了NaF-KF-UF三元体系中两种共晶成分的新数据,这两种成分可作为熔盐反应堆潜在的燃料候选物。实验测量包括它们的熔点、密度、熔化焓和蒸气压。此外,它们的沸点是从蒸气压数据推断出来的,同时这些数据还用于确定汽化焓。将获得的热力学值与文献中的现有数据以及使用JRCMSD数据库进行的热化学平衡计算结果进行了比较,发现有良好的相关性,这有助于数据库验证。本研究还讨论了基于所得结果对氟化物盐反应堆可操作性的初步想法。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/9e231adaf44d/materials-17-02776-g009.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/f90c9bec42dc/materials-17-02776-g001.jpg
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https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/57e0e34d1b51/materials-17-02776-g004.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/71f485836dda/materials-17-02776-g005.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/49d3e2863174/materials-17-02776-g006.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/bf7cfaafc299/materials-17-02776-g007.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/dbb32c86a496/materials-17-02776-g008.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/9e231adaf44d/materials-17-02776-g009.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/f90c9bec42dc/materials-17-02776-g001.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/53a18d920212/materials-17-02776-g002.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/22b2f91fac41/materials-17-02776-g003.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/57e0e34d1b51/materials-17-02776-g004.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/71f485836dda/materials-17-02776-g005.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/49d3e2863174/materials-17-02776-g006.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/bf7cfaafc299/materials-17-02776-g007.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/dbb32c86a496/materials-17-02776-g008.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/db66/11173649/9e231adaf44d/materials-17-02776-g009.jpg

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本文引用的文献

1
Cesium and iodine release from fluoride-based molten salt reactor fuel.基于氟化物的熔盐反应堆燃料中铯和碘的释放。
Phys Chem Chem Phys. 2021 Apr 22;23(15):9512-9523. doi: 10.1039/d0cp05794k.