Mobile Emergency Cooling System for Nuclear Reactor Decay Heat
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Solution Overview
Problem
Nuclear power generating facilities face prolonged shutdowns and increased costs due to the need for extended operation of residual heat removal systems during refueling, and there is a need for a rapid and cost-effective solution to cool spent fuel pools, especially in emergency situations like power outages.
Innovation Solution
A self-powered, mobile residual heat removal system that includes a primary fluid heat exchange system with a closed loop configuration, a portable electric generator, and a secondary cooling loop that can be rapidly connected and disconnected, allowing for independent operation outside the reactor containment and providing make-up water to the spent fuel pool.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Reliability
If the permanent residual heat removal system is operated for multiple days to cool the reactor core, then the fuel can be safely removed to the spent fuel pool, but the shutdown period is extended and facility costs increase
Solution Approach 1:
The patent applies preliminary action by pre-positioning an auxiliary cooling system within the containment structure that can be rapidly activated. This system includes pre-installed heat exchangers and piping that can immediately augment cooling capacity when needed, eliminating the need for multi-day operation of the permanent system and reducing shutdown time while maintaining safe fuel removal conditions
2Productivity
If the cooling capacity of the spent fuel pool system is increased, then the fuel can be cooled more rapidly, but the system cost increases significantly
Solution Approach 1:
The patent applies segmentation by dividing the cooling system into modular components - a permanent base system and an auxiliary augmenting system. The auxiliary system consists of separate, independently installable units with their own heat exchangers and circulation equipment, allowing capacity to be increased incrementally only when needed rather than building an oversized permanent system, thus controlling costs while improving cooling rate
3Power
If the auxiliary cooling system is permanently installed within the containment, then the cooling capacity is available, but the system complexity and installation cost increase
Solution Approach 1:
The patent applies dynamics by designing an auxiliary cooling system that transitions from a static permanent installation to a dynamic, adaptable configuration. The system includes rapidly deployable modular units that can be installed or removed based on operational needs, with flexible piping and connections that adapt to different operational scenarios, providing high cooling capacity when needed while maintaining simpler system configuration during normal operation
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 reduces the time required for cooling the reactor core, decreases shutdown periods, and spreads the cost of the cooling system across multiple facilities, enabling rapid deployment and operation during emergencies, such as power losses, without the need for extensive modifications to existing infrastructure.
Implementation Method 1
A heat exchanger is provided which includes a primary fluid inlet and a primary fluid outlet both communicatively coupled to the reactor core, and a secondary fluid inlet and a secondary fluid outlet
Implementation Method 2
A portable electric generator is provided which is adapted to provide power to the secondary cooling loop
Data Source
AI summary
An emergency temporary spent fuel pool cooling system for a nuclear power generating facility that has a permanently installed primary loop within the nuclear containment and a mobile temporary secondary loop. The secondary loop is housed in transport vehicles that can be stored off site and is connectable in heat exchange relationship with the primary loop through quick disconnect couplings that are accessible on the outside of the reactor containment. The transport vehicles also include self-contained power and compressed air sources for powering and controlling the entire emergency cooling system. The system also has a make-up water injection capability for refueling the spent fuel pool and secondary loop.