Variable Area Heat Pipe Network for Nuclear Reactor Cooling
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Solution Overview
Problem
Nuclear reactor designs using heat pipes for heat removal from a core of nuclear material are limited by the constant heat pipe flow area, which restricts heat removal capacity and displaces fuel, reducing the core's heat production potential.
Innovation Solution
A network of interconnected heat pipes with an increasing cross-sectional flow area from the evaporator region to the condenser region, allowing for enhanced heat removal capacity while minimizing displacement of nuclear fuel.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Productivity
If a larger number of heat pipes are used to increase total effective flow area and heat removal capacity, then heat removal capacity is improved, but fuel and other core material are displaced, reducing heat production potential
Solution Approach 1:
The heat pipe system is divided into multiple discrete heat pipes rather than using a single large heat pipe. This segmentation allows the heat pipes to be distributed throughout the core in a pattern that minimizes fuel displacement while collectively providing sufficient total flow area for high heat removal capacity
Solution Approach 2:
The invention transitions from considering only the cross-sectional flow area to incorporating the spatial distribution dimension. By arranging heat pipes in specific three-dimensional configurations within the core, the system achieves high heat removal capacity without requiring excessive heat pipe volume that would displace fuel
2Ease of manufacture
If constant heat pipe flow area is used in discreet unconnected heat pipes, then manufacturing and assembly are simplified, but heat removal capacity is limited
Solution Approach 1:
The invention changes the flow area parameter from constant to variable along the length of the heat pipes. Specifically, the flow area increases in the direction of heat flow, which enhances heat removal capacity while the heat pipes remain discrete and unconnected for manufacturing simplicity
Applied Scientific Principles
This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.
Function Achieved in This Case
The increasing flow area design increases the heat removal capacity of the heat pipes, allowing for more efficient heat transfer without displacing significant amounts of fuel, thereby optimizing the reactor's power output.
Implementation Method 1
a heat pipe network including an evaporator region, an adiabatic region, and a condenser region... configured to transfer the heat from the evaporator region to the condenser region
Implementation Method 2
The heat pipes are configured to contain a working fluid... transfer the heat from the evaporator region to the condenser region
Data Source
AI summary
Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a heat pipe network having an evaporator region, an adiabatic region, and a condenser region. The heat pipe network can define a plurality of flow paths having an increasing cross-sectional flow area in a direction from the evaporator region toward the condenser region. The system can further include nuclear fuel thermally coupled to at least a portion of the evaporator region. The heat pipe network is positioned to transfer heat received from the fuel at the evaporator region, to the condenser region. The system can further include one or more heat exchangers thermally coupled to the evaporator region for transporting the heat out of the system for use in one or more processes, such as generating electricity.