Passive Nuclear Cooling Loop With Steam Condensation Return
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Solution Overview
Problem
Current long-term cooling systems in nuclear power plants rely on large-scale seawater cooling facilities, which are costly and limited by the need for seawater proximity, and can fail without operational pumps, posing risks like nuclear fuel melting or hydrogen explosions.
Innovation Solution
A long-term cooling system utilizing an Emergency Cooling Tank (ECT) and Gas-Liquid Separator within the nuclear power plant, allowing for air-cooled condensation of steam and separation of non-condensable gases, enabling continuous cooling without seawater and pump operation.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Temperature
If large-scale seawater cooling facilities are used for long-term cooling, then cooling performance is improved, but construction cost increases and location is limited
Solution Approach 1:
The patent extracts the essential cooling function from the complex seawater cooling system by using the existing IRWST and its heat exchanger for long-term cooling, eliminating the need for separate large-scale seawater cooling facilities
Solution Approach 2:
The IRWST, originally designed for refueling operations, is made multi-functional by enabling it to serve as a long-term cooling reservoir through its existing heat exchanger, allowing it to perform both refueling water storage and residual heat removal functions
2Temperature
If seawater cooling facilities are used for long-term cooling, then cooling capability is improved, but location flexibility deteriorates
Solution Approach 1:
The system uses internally available resources (the IRWST and its heat exchanger already present in the nuclear power plant) to perform long-term cooling, eliminating dependence on external seawater resources and enabling the plant to be located anywhere
3Productivity
If pumps are used to circulate seawater for cooling, then cooling efficiency is improved, but system reliability deteriorates
Solution Approach 1:
The patent replaces the mechanical pump-based seawater circulation system with a passive cooling system that uses natural convection and the existing IRWST infrastructure, eliminating mechanical failure points and improving reliability
Solution Approach 2:
The system discards the active pump mechanism and recovers the cooling function through passive heat exchange processes, using the IRWST and its heat exchanger to naturally remove residual heat without requiring mechanical circulation
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
This system effectively manages residual heat from nuclear reactors during accidents by eliminating the need for seawater cooling facilities and pump operation, ensuring safety and efficiency in cooling performance.
Implementation Method 1
a condensation heat exchanger, steam and air within the first boundary area are introduced into the condensation heat exchanger... at least part of the introduced steam is condensed
Implementation Method 2
an emergency cooling tank provided with a condensation heat exchanger... steam and air within the first boundary area are introduced into the condensation heat exchanger
Implementation Method 3
a gas-liquid separator... connected to the emergency cooling tank... separating non-condensable gases from condensate
Data Source
AI summary
A cooling system in a nuclear power plant is disclosed, including a boundary section disposed inside a containment to enclose a reactor coolant system, and configured to restrict steam containing radioactive materials generated in the reactor coolant system from leaking into paths other than a discharge part. An In-Containment Water Storage Tank (IRWST) is disposed outside the boundary section and is configured to store refueling water therein. An emergency cooling tank is disposed outside the containment and is provided with a condensation heat exchanger. A gas-liquid separator is connected to the emergency cooling tank outside the containment. A return line is configured to connect the gas-liquid separator and the boundary section such that condensate generated by condensing the steam within the boundary section, through the emergency cooling tank and the gas-liquid separator, is discharged toward the boundary section upon an occurrence of a nuclear power plant accident.