External-cooling full-height comprehensive test platform for large-scale advanced reactor pressure vessel

Abstract

The invention provides an external-cooling full-height comprehensive test platform for a large-scale advanced reactor pressure vessel. The test platform comprises a main device loop system, a condensing and cooling system, a water supply and preheating system, a water chemistry adjusting system and a pressure control system, the condensing and cooling system is used for controlling and adjusting temperature of primary fluid in an upper water tank of the main device loop system and providing circularly cooling for test water in the upper water tank, the water supply and preheating system is used for providing the test water to the main device loop system, initially preheating the test water and keeping temperature, the water chemistry adjusting system is communicated with a lower water tank of the main device loop system and used for controlling solute and concentration of water chemistry solution in different tests, and the pressure control system is used for controlling pressure of the upper water tank. According to the test platform, engineering verification test of value and distribution of boiling heat transfer limit CHF (critical heat flux) of the outer wall of a lower sealing head of the pressure vessel can be determined when IVR-ERVC (in-vessel retention-external reactor vessel cooling) is implemented under severe accident conditions.

Description

technical field [0001] The invention relates to a full-height test platform for external cooling of reactor pressure vessels, in particular to a full-height comprehensive test platform for external cooling of large-scale advanced reactor pressure vessels. Background technique [0002] As one of the important measures for severe accident management, in-reactor melt retention (IVR) takes pressure vessel (RPV) external cooling measures (ERVC) for the reactor to remove heat from the melt and keep the melt in the RPV. [0003] Typical international test benches for researching IVR-ERVC mainly include ULPU series test benches and SBLB benches. Among them, ULPU series benches (I, II, III) are mainly designed for the geometric structure and overall design parameters of AP600, while IV and V are mainly designed for AP1000. The SBLB bench performs three-dimensional scaling design on the size of the prototype pressure vessel, and then simulates the external cooling limit of the pressu...

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Problems solved by technology

[0006] my country's large-scale advanced pressurized water reactor CAP1400 also considers adopting passive IVR-ERVC, a severe accident mitigation scheme, because the power of CAP1400 is significantly improved compared with AP1000, and the uneven thermal load on the wall leads to an increase in the local thermal load inside the RPV under severe accidents. This poses a major challenge to the capabilities of ERVC

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