Nuclear Reactor Equipment Transfer Apparatus with Rolling Parts
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Solution Overview
Problem
Existing management equipment transfer systems for nuclear reactor vessels are inflexible and cumbersome, requiring separate brackets for size adjustments and limiting the number of reactors that can be tested, with difficulty in decomposition, assembly, and transfer due to fixed platforms and non-modular multi-axis manipulators.
Innovation Solution
A management equipment transfer apparatus with a cross beam, rod, bracket, and arm system that can be expanded or contracted, featuring rolling parts and actuators to automatically adjust and support equipment within the reactor vessel, allowing for independent installation and transfer regardless of vessel size, and enabling easy replacement and storage of test and maintenance equipment.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If a fixed platform is used to install management equipment, then the equipment can be securely mounted, but the system becomes difficult to decompose, assemble, and transfer between different nuclear reactor vessels
Solution Approach 1:
The management equipment transfer apparatus is divided into separate modular components: a transfer apparatus with rolling parts for movement, a manipulator for positioning, and a bracket for equipment mounting. This segmentation allows each component to be independently assembled and disassembled, enabling easy transfer between different nuclear reactor vessels while maintaining secure mounting capability through the dedicated bracket component.
2Adaptability or versatility
If a fixed platform with separate brackets is used, then the equipment can be adjusted for different sizes, but the system complexity increases and transferability decreases
Solution Approach 1:
The transfer apparatus incorporates rolling parts that can engage with the inner peripheral surface of nuclear reactor vessels of various sizes, providing universal adaptability. The manipulator and bracket system can be positioned at different locations along the transfer apparatus, allowing adjustment for different equipment sizes and vessel configurations without requiring separate brackets or complex reconfiguration, thereby reducing overall system complexity.
3Manufacturing precision
If a non-modular multi-axis manipulator is used, then the equipment can be positioned precisely, but the number of reactors that can be tested is limited and transfer is difficult
Solution Approach 1:
The manipulator is designed with dynamic positioning capability, allowing it to be repositioned along the transfer apparatus between different nuclear reactor vessels. The rolling parts provide dynamic movement along the inner peripheral surface, while the manipulator maintains precise positioning control. This dynamic design enables the same apparatus to serve multiple reactors without requiring permanent installation or complex disassembly, increasing the number of testable reactors.
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 apparatus allows for flexible installation and transfer of management equipment, reducing weight and volume, and enabling automatic operation, thus enhancing the efficiency and versatility of nuclear reactor vessel testing and maintenance.
Implementation Method 1
rolling parts configured to be disposed at ends of the arm and the cross beam, contact the inner peripheral surface of the nuclear reactor vessel, and rotatably support the cross beam and the arm
Data Source
AI summary
A management equipment transfer apparatus which transfers management equipment, which tests and maintains an inside of a nuclear reactor vessel, inside the nuclear reactor vessel while being locked to the management equipment and the nuclear reactor vessel, includes: a cross beam configured to be lengthily disposed inside the nuclear reactor vessel in a transverse direction; a rod configured to be connected to a cross beam lengthily disposed inside the nuclear reactor vessel in a longitudinal direction; a bracket configured to be mounted in the rod to fix the management equipment; an arm configured to extend toward an inner peripheral surface of the nuclear reactor vessel and be connected to the cross beam; and rolling parts configured to be disposed at ends of the arm and the cross beam, contact the inner peripheral surface of the nuclear reactor vessel, and rotatably support the cross beam and the arm.