压水堆核电厂压力容器内空泡份额测量方法及装置
By using an external nuclear neutron flux measurement device in a pressurized water reactor (PWR) nuclear power plant to calculate the amplification factor and fitting formula, the problems of measurement error and reliability of the void fraction in the pressure vessel were solved. This enabled accurate measurement and timely assessment of the void fraction in the pressure vessel of a PWR nuclear power plant, ensuring safe management during severe accidents.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- CHINA NUCLEAR POWER DESIGN COMPANY
- Filing Date
- 2022-12-12
- Publication Date
- 2026-07-17
AI Technical Summary
Existing methods for measuring the void fraction within the pressure vessel of pressurized water reactor nuclear power plants have significant measurement errors and insufficient reliability. In particular, during severe accidents when the core cooling condition deteriorates, existing instruments cannot accurately monitor the void fraction.
By constructing a method for measuring the void fraction inside the pressure vessel of a pressurized water reactor nuclear power plant, the core neutron flux level is monitored using an external nuclear neutron flux measurement device. The amplification factor is calculated and a measurement formula is generated by fitting. Combined with a physical model and validity verification, the accurate measurement of the void fraction is achieved.
Without altering the existing pressure vessel and core design, it provides accurate measurement of the void fraction within the pressure vessel, ensuring timely and accurate assessment of the core cooling status during severe accidents, enabling the selection of appropriate emergency strategies, and effectively limiting the consequences of accidents.
Smart Images
Figure CN115798753B_ABST