AI Summary of Peer-Reviewed Research
This page presents an AI-generated summary of a published research paper. The original authors did not write or review this article. See full disclosure ↓
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- ✔ Peer-reviewed source
- ✔ Published in indexed journal
- ✔ No retraction or integrity flags
Overview
This research addresses molten lead-bismuth eutectic (LBE) permeation through graphite coolant channel materials in lead-cooled fast reactors by employing a modification process based on precursor impregnation and pyrolysis. The study evaluates the effectiveness of polycarbosilane-derived surface modification in reducing infiltration rates and improving structural integrity of commercial nuclear graphite under conditions relevant to LFR operation.
Methods and approach
Commercial nuclear graphite specimens underwent modification through impregnation with polycarbosilane solution followed by pyrolysis to generate a silicon carbide coating. Structural and infiltration characteristics of both pristine and modified graphite samples were assessed using mercury infiltration experiments and static molten LBE infiltration testing across multiple pressure conditions. Comparative analysis evaluated differences in pore structure compactness and resistance to molten salt penetration between treated and untreated materials.
Key Findings
The polycarbosilane-based modification process substantially increased structural compactness of the graphite substrate and reduced infiltration resistance to molten LBE across all applied pressures. Modified graphite samples exhibited markedly lower molten LBE uptake compared to pristine graphite. The silicon carbide coating derived from polycarbosilane precursor demonstrated adequate durability and stability during extended exposure to molten LBE infiltration conditions, maintaining its protective function without degradation.
Implications
The precursor impregnation and pyrolysis modification approach represents a viable technical solution for developing graphite coolant channel materials suitable for lead-cooled fast reactor systems. The method addresses a critical operational challenge by substantially mitigating permeation-related risks that could compromise reactor performance and safety during extended operation. Further development of this surface modification technique could enhance material performance specifications for LFR applications.
Disclosure
- Research title: Improving the impermeability of nuclear graphite towards molten lead-bismuth eutectic in lead-cooled fast reactor by precursor impregnation and pyrolysis processes
- Authors: Zhao He, Jinliang Song, Zhanjun Liu
- Institutions: Chinese Academy of Sciences, Institute of Coal Chemistry, King Abdullah University of Science and Technology, Shanghai Institute of Applied Physics
- Publication date: 2026-03-07
- DOI: https://doi.org/10.1016/j.net.2026.104250
- OpenAlex record: View
- Image credit: Photo by Energie-portal.sk on Unsplash (Source • License)
- Disclosure: This post was generated by Claude (Anthropic). The original authors did not write or review this post.
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