Thermal bridge

A thermal bridge of graphitic carbon in the fuel channel gap addresses inefficiencies in high temperature gas cooled reactors, enhancing thermal transfer and reactor efficiency while using nitrogen coolant, compatible with existing turbomachinery.

GB2603000BActive Publication Date: 2026-07-02BAE SYSTEMS PLC

Patent Information

Authority / Receiving Office
GB · GB
Patent Type
Patents
Current Assignee / Owner
BAE SYSTEMS PLC
Filing Date
2021-01-25
Publication Date
2026-07-02

AI Technical Summary

Technical Problem

High temperature gas cooled nuclear reactors face inefficiencies due to fuel channel gaps and the use of low thermal conductivity coolants like nitrogen, which reduce thermal transfer and overall reactor efficiency, and the immaturity of turbomachinery designs for helium coolant poses a commercial barrier.

Method used

Incorporating a thermal bridge made of powdered material, such as graphitic carbon, within the fuel channel gap to enhance thermal transfer between the fuel element and the fuel channel, while using nitrogen as a coolant compatible with existing turbomachinery, and optionally incorporating a burnable poison like boron carbide to manage neutron reactivity.

Benefits of technology

Improves thermal conductivity and reactor efficiency by maintaining thermal contact despite volumetric changes, reduces the need for increased coolant flow, and enhances compatibility with conventional turbomachinery, thereby increasing overall reactor performance.

✦ Generated by Eureka AI based on patent content.

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Abstract

A thermal bridge 510 is provided between a fuel element 508 and a fuel channel 506 in a high temperature gas cooled nuclear reactor (HTGR) 500 in order to improve thermal transfer between the fuel ele
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