Micro-Reactor Fuel Sleeve Assembly for Fast Compact Extraction
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Solution Overview
Problem
Insertion and extraction of TRISO fuel compacts in nuclear micro-reactors is time-consuming and challenging, requiring a non-vertical orientation to avoid damage, complicating fuel loading, re-fueling, and end-of-life processing, and increasing the risk of compacts becoming stuck in the core.
Innovation Solution
A fuel sleeve assembly is used to house fuel compacts, featuring a sleeve, end caps, and a biasing member, with an extraction tool interface, allowing for efficient automated insertion and extraction of the entire assembly, reducing installation and decommissioning time, and simplifying waste separation.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If TRISO fuel compacts are inserted individually in a non-vertical orientation to avoid damage, then the fuel compacts are protected from damage, but the fuel loading process becomes time-consuming and complex
Solution Approach 1:
The fuel loading system is segmented into modular components: a loading guide that maintains non-vertical orientation, individual compact holders, and a systematic insertion path. This segmentation allows each fuel compact to be handled separately with proper orientation protection while organizing the process into efficient stages, resolving the contradiction between careful individual handling and overall loading speed.
Solution Approach 2:
The loading guide pre-establishes the correct non-vertical insertion path and orientation before fuel compacts are introduced. By preparing the insertion trajectory and orientation constraints in advance, the system eliminates the need for slow, careful manual positioning during actual loading, thus protecting fuel compact integrity while maintaining loading productivity.
2Reliability
If TRISO fuel compacts are inserted in a non-vertical orientation, then the fuel compacts avoid damage, but the insertion and extraction process becomes challenging and time-consuming
Solution Approach 1:
A loading guide and extraction tool act as intermediary devices between the operator and the fuel compacts. These intermediaries maintain the required non-vertical orientation and provide mechanical assistance for insertion and extraction, making the process easier to operate while ensuring fuel compact integrity is protected throughout the operation.
Solution Approach 2:
The system pre-configures the insertion and extraction paths with proper orientation constraints through the loading guide. By establishing the correct angular orientation and mechanical guidance in advance, the system simplifies the operational process while maintaining fuel compact protection, eliminating the need for complex manual positioning during actual insertion and extraction.
3Productivity
If fuel loading and extraction processes are simplified, then the time for initial fuel loading and re-fueling is minimized, but the risk of compacts becoming stuck in the core increases
Solution Approach 1:
The loading guide and extraction tool serve as intermediary mechanisms that simplify the fuel loading and extraction processes while maintaining proper orientation and control. These intermediaries provide mechanical guidance and force distribution that prevent compacts from becoming stuck during simplified high-speed operations, thus resolving the contradiction between loading efficiency and stuck risk.
Solution Approach 2:
The system replaces manual, error-prone mechanical handling with a controlled mechanical guidance system (loading guide and extraction tool). This substitution provides consistent, repeatable insertion and extraction paths that simplify operations while eliminating the variability and risk associated with manual handling, preventing compacts from becoming stuck during efficient fuel loading.
Data Source
AI summary
Disclosed is nuclear reactor fuel rod for use in a nuclear reactor. The nuclear reactor fuel rod comprises a sleeve defining a longitudinal axis. The sleeve includes a first end portion and a second end portion. The nuclear reactor fuel rod further includes a first end cap mechanically coupled to the first end portion of the sleeve and a second end cap mechanically coupled to the second end portion of the sleeve. The second end cap is configured to slide along the longitudinal axis relative to the sleeve. The nuclear reactor fuel rod further includes a fuel compact located inside of the sleeve between the first end cap and the second end cap.