Method for calculating safety valve threshold of reactor cold overpressure stabilizer

Abstract

The invention discloses a method for calculating a safety valve threshold of a reactor cold overpressure stabilizer. The method mainly comprises the following steps: 1, establishing a thermal hydraulic model by utilizing a nuclear reactor thermal hydraulic system analysis program; 2, verifying the reliability of the model through the standard operation condition of the reactor; if the model is unreliable, returning to the step 1, and readjusting the model; 3, determining an allowable operation pressure range of the reactor; 4, setting a cold overpressure transient working condition and supposing an initial opening and closing value of the valve; 5, judging the most dangerous part of the reactor pressure vessel and obtaining a transient P-T curve of the most dangerous part; 6, continuouslyadjusting the opening and closing pressure of the valve, comparing the transient P-T curve with the allowable operation pressure range of the reactor in the step 3 until the maximum closing pressure and the minimum opening pressure of the valve are found, and obtaining a reasonable valve threshold value. According to the cold overpressure valve threshold value calculation method, the influence ofvarious key factors under a cold overpressure accident is comprehensively considered, the valve threshold value is more conservatively and effectively calculated, and a basis is provided for reactor safety design.

Description

technical field [0001] The invention relates to the field of nuclear reactor design calculations, in particular to a method for calculating the safety valve threshold of a reactor cold overpressure regulator. Background technique [0002] As the largest part of the primary circuit, the pressure vessel may be accompanied by some critical size cracks, which will undergo brittle fracture once they are subjected to sufficient pressure or a large impact force at low temperature. When the pressure vessel breaks, it will no longer be able to provide sufficient coolant for cooling the core, which will eventually lead to fuel element damage or even a core melting accident, with disastrous consequences. This issue thus affects the design and operation of all nuclear power plants. [0003] The cooling and depressurization process of the primary circuit during the normal shutdown of the reactor is divided into two stages. The first stage: the pressurizer is in the two-phase stage of st...

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Problems solved by technology

[0005] The technical problem to be solved by the present invention is that the calculation method for the cold overpressure valve threshold of the reactor in the prior art is relatively lacking, and there is a certain gap in the field of cold overpressure in domestic power stations, and it is impossible to correctly obtain the threshold value of the pressure stabilizer safety valve under low temperature conditions. The setting value of the reactor affects the safety of the reactor

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