A test platform for structural integrity of reactor pressure vessel under ivr conditions

Abstract

The invention discloses a platform for testing the structural integrity of a reactor pressure vessel under an IVR condition. The platform comprises a working condition simulation system, a data acquisition and analysis system, and a safety system. The working condition simulation system is provided with a water supply unit, a steam condensing unit, and a heating unit; the data acquisition system is composed of measuring elements of each unit; and the safety system is arranged on the periphery of the working condition simulation system. The boiling heat transfer process in a reactor pressure vessel can be simulated by controlling the water flow of a cooling unit and the heating power of a hot pool simulation unit; by measuring and simulating the wall temperature, strain, and pressure, the heat transfer characteristics of a reactor pressure vessel can be simulated and analyzed; a referential model is provided for the boiling heat transfer tests on a reactor pressure vessel; and the test platform has a simple and compact structure, can carry out structural integrity analysis on a simulated reactor pressure vessel, comprises a nitrogen gas pressurizing unit, thus can also carry out analysis on the heat transfer characteristics of a pressurized reactor pressure vessel, and has a wide application range.

Description

technical field [0001] The invention belongs to the technical field of a structural integrity test platform, and in particular relates to a structural integrity test platform of a reactor pressure vessel under IVR conditions with high precision, reliable control, simple test and the ability to simulate multiple working conditions of the reactor pressure vessel. Background technique [0002] In Vector Retention (IVR for short) refers to cooling the core from outside the reactor pressure vessel so that the core melt stays in the reactor pressure vessel. This is a very important severe accident mitigation measure for nuclear power plants, and the reactor pressure vessel is the heart of the nuclear power plant, so it is very important to ensure the structural integrity of the nuclear reactor pressure vessel. However, in the actual assumed conditions, in order to ensure the success of IVR, the following measures must be taken in the design: the reactor coolant system is depressur...

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Problems solved by technology

However, the above assumptions are the most ideal situation. If the reactor coolant system is not fully depressurized (that is, there is a certain internal pressure in the reactor pressure vessel), how to ensure the success of IVR? Can the cooling water take away the residual heat in the reactor within the specified time? In the IVR evaluation, the actual heat flux and critical heat flux on the outer wall of the reactor pressure vessel must be calculated and compared. If the actual value exceeds the critical value, it is assumed that the reactor pressure vessel fails

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