用于三iso燃料生产的FB-CVD制备SiC的性能综述

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-04-05 DOI:10.1016/j.pnucene.2025.105762

Linyi Hu , Joel Turner , James Buckley , Tim Abram

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引用次数: 0

摘要

为了在2050年前实现净零排放，需要一种稳定、可持续的绿色能源。对“核复兴”的重新关注凸显了在本世纪30年代初展示高温气冷堆（HTGR）技术的重要性。htgr的性能取决于其先进燃料形式的质量，即三结构各向同性（TRISO）涂层燃料颗粒。尽管TRISO颗粒的制造在20世纪后期取得了成功，但缺乏商用HTGR系统限制了这种先进燃料形式的发展，特别是在英国龙计划终止后。全球范围内活跃的研究机构数量较少，导致对制造过程缺乏基本的机械理解，从而增加了将生产扩大到工业水平的不确定性。曼彻斯特大学的活性流化床化学气相沉积（FB-CVD）涂层机的调试强调了对制造参数（沉积温度、气体成分、流速等）进行初步文献研究的必要性，这些参数对于实现高质量的TRISO产品至关重要，同时考虑到实验铀材料的经济利用。本研究分为两部分，分别关注碳化硅（SiC）层和热解碳（PyC）层。在目前的工作中，SiC的性能（化学计量、微观结构、密度）和工艺参数（涂层速率、效率）被仔细检查。从历史和最近的FB-CVD涂层世界各地的实验结果进行了分析，建立了制造参数，SiC性能和工艺结果之间的相关性。关于沉积温度的影响存在共识，尽管关于H2/MTS的影响观察到相互矛盾的结果。其他关键的制造参数，如输入气体流速仍有待确定。

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A review on properties required for FB-CVD fabricated SiC for TRISO fuel production

In pursuit of achieving Net-Zero by 2050, there is a demand for a stable, sustainable source of green energy. The renewed focus on a ‘nuclear renaissance’ has highlighted the importance of demonstrating High Temperature Gas-cooled Reactor (HTGR) technology by the early 2030s. The performance of HTGRs hinges on the quality of their advanced fuel form known as TRi-structural ISOtropic (TRISO) coated fuel particles.

Although the fabrication of TRISO particles achieved success in the late 20th century, the lack of commercial HTGR systems limited the development of this advanced fuel form, particularly in the UK after the termination of the Dragon Project. The small number of active research facilities globally has resulted in a lack of fundamental mechanistic understanding of the fabrication process, contributing to uncertainties in scaling up production to an industrial level.

The commissioning of an active Fluidised Bed Chemical Vapour Deposition (FB-CVD) coater at the University of Manchester underscores the necessity for a preliminary literature study on fabrication parameters (deposition temperature, gas composition, flow rate, etc.) crucial for achieving high-quality TRISO products, while considering the economical utilisation of experimental uranic materials. This study is presented in two parts focusing on silicon carbide (SiC) and pyrolytic carbon (PyC) layers respectively.

In the present work, SiC properties (stoichiometry, microstructure, density) and process parameters (coating rate, efficiency) are scrutinised. Experimental findings from historical and recent FB-CVD coaters worldwide have been analysed to establish correlations between fabrication parameters, SiC properties, and process outcomes. Consensus exists regarding the influence of deposition temperature, though conflicting results are observed concerning the impact of H₂/MTS. Other crucial fabrication parameters such as input gas flow rates remain to be definitively determined.

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.