Steam Generator Accident Mitigation via Pressurizing Tank
Find Innovative SolutionsGenerate Solutions
Solution Overview
Problem
Current technologies lack effective means to prevent the release of radioactive materials into the atmosphere during steam generator tube rupture accidents in nuclear reactors, leading to uncontrolled radioactive material release and pressure fluctuations in steam generators.
Innovation Solution
A steam generator accident mitigation system comprising a pressurizing tank with first and second cooling waters and non-condensable gases, connected to the steam generator via pipes and valves, allowing controlled fluid communication to redirect steam or cooling water between the steam generator and pressurizing tank, and a safety valve to release steam into a containment building, minimizing radioactive material release.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Stress or pressure
If a steam generator tube rupture accident occurs and safety valves are opened, then pressure is relieved, but radioactive materials are released directly into the atmosphere
Solution Approach 1:
The invention introduces a containment building as an intermediary structure between the steam generator and the atmosphere. When a tube rupture occurs, the safety valve releases steam and radioactive materials into the containment building rather than directly into the atmosphere. The containment building acts as a temporary holding space that prevents direct atmospheric release while allowing pressure relief to occur.
Solution Approach 2:
The invention converts the harmful effect of uncontrolled atmospheric release into a beneficial containment scenario. By directing the released steam and radioactive materials into the containment building, the system transforms what would be an uncontrolled environmental hazard into a controlled situation where the radioactive materials are confined within the containment structure, preventing external contamination.
2Stress or pressure
If atmospheric dump valves or safety valves are opened during tube rupture, then steam pressure is reduced, but radioactive materials escape to the environment
Solution Approach 1:
The containment building serves as a mediator that intercepts the steam and radioactive materials before they can reach the environment. The safety valve remains functional for pressure relief, but the containment building blocks the direct path to the atmosphere, thus maintaining pressure control while preventing environmental contamination.
3Ease of operation
If current emergency response procedures are used, then operator response is coordinated, but there is no active facility to suppress radioactive material release
Solution Approach 1:
The containment building is pre-installed and pre-configured within the steam generator system before any accident occurs. This preliminary structural preparation ensures that when a tube rupture happens, the containment building is already in position to capture and hold radioactive materials, eliminating the need for complex active suppression facilities or procedures during the emergency.
Solution Approach 2:
The containment building provides automatic, passive containment functionality that operates without requiring complex active control systems or additional operational interventions. Once the safety valve opens and releases materials into the containment building, the structure automatically contains the radioactive materials through its physical barrier, providing self-service containment functionality.
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 system effectively limits the release of radioactive materials to the outside environment by redirecting steam or cooling water within the containment building, reducing the risk of atmospheric contamination and managing pressure fluctuations during accidents.
Implementation Method 1
a pressurizing tank which is installed inside the containment building and comprises a first cooling water and a non-condensable gas for pressurizing the first cooling water therein
Implementation Method 2
in case the pressure inside the steam generator increases due to accidents, the second cooling water or the steam may be configured to move from the steam generator to the pressurizing tank by a pressure difference
Implementation Method 3
a first safety valve installed on one end of the pressurizing tank outside, and at least some of steam introduced from the steam generator into the pressurizing tank may be configured to be released inside the containment building through the first safety valve
Data Source
AI summary
A steam generator accident mitigation system is disclosed. A steam generator accident mitigation system to mitigate an accident if the accident occurs in a steam generator installed inside a containment building of a nuclear power plant according to an exemplary embodiment of the present system, the system including: a pressurizing tank which is installed inside the containment building and includes a first cooling water and a non-condensable gas for pressurizing the first cooling water therein; at least one connecting pipe connecting the steam generator and the pressurizing tank; and at least one connecting pipe valve which is installed in the at least one connecting pipe, respectively, and is able to control the amount of opening of the connecting pipe; wherein opening of the at least one connecting pipe valve permits fluid communication between the steam generator and the pressurizing tank.