Method for analyzing severe accident of pressurized water reactor (PWR) nuclear power plant

A technology for serious accidents and analysis methods, applied in electrical digital data processing, special data processing applications, instruments, etc., can solve problems such as high difficulty and high cost

Active Publication Date: 2017-12-08
XI AN JIAOTONG UNIV
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Problems solved by technology

At present, there is no comprehensive analysis software for large-scale advanced pressurized water reactor severe accidents with independent inte

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  • Method for analyzing severe accident of pressurized water reactor (PWR) nuclear power plant
  • Method for analyzing severe accident of pressurized water reactor (PWR) nuclear power plant
  • Method for analyzing severe accident of pressurized water reactor (PWR) nuclear power plant

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Embodiment Construction

[0240] The method of the present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0241] Such as figure 1 Shown, the severe accident analysis method and technical method of the pressurized water reactor nuclear power plant of the present invention comprise the following steps:

[0242] Step 1: Calculate the core behavior characteristics and fuel assembly stress-strain characteristics in the early stages of severe accidents, and calculate the distribution temperature of each core node, the oxidation amount of the core cladding, the mass of hydrogen produced, and the rate of change of the stress and strain of the fuel cladding. Such as figure 2 As shown, the calculation of early core behavior characteristics and fuel assembly stress-strain characteristics specifically includes the following contents:

[0243] 1) Read thermal-hydraulic parameters and response information of the core in all accident phases;

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Abstract

A method for analyzing a severe accident of a PWR nuclear power plant comprises: 1. calculating a behavioral characteristic of an early-stage core and a stress-strain characteristic of a fuel assembly of a severe accident; 2. calculating core melting; 3. calculating a core debris bed characteristic; and 4. analyzing and calculating a configuration of a melting matter in a head of a pressure vessel, wherein, a heat transfer between the melting matter and a surrounding material is calculated by a Runge-Kutta method at first, then steam flow that is released from the melting matter to the core during a cooling convection process is calculated, then mass and energy exchange between particles of the melting matter and a surrounding environment is calculated, and finally heat flow from a debris hard shell is calculated according to an inner temperature of the hard shell. Based on analysis of the mechanism and sequence of the severe accident of the large pressurized water reactor, management strategies and mitigation measures for severe accidents applicable to pressurized water reactors in our country are put forward, and technical support is offered for formulation of safety strategies of severe accidents of nuclear power plants in our country.

Description

technical field [0001] The invention belongs to the field of calculation of severe accident phenomena of reactors, and in particular relates to a method for analyzing severe accidents of pressurized water reactor nuclear power plants. Background technique [0002] Severe accidents in nuclear power plants may cause a large amount of radioactive material to leak, resulting in huge economic losses and adverse social consequences. There have been three serious nuclear power plant accidents on the road to the peaceful use of nuclear energy by mankind: the Three Mile Island accident in the United States (1979), the Chernobyl accident in the former Soviet Union (1986), and the Fukushima nuclear power plant accident in Japan (2011). The nuclear accident will cast a heavy shadow on the global recovery of nuclear power in this century. [0003] In recent years, my country's nuclear power has developed rapidly. In order to change my country's existing energy structure, enhance energy ...

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Application Information

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IPC IPC(8): G06F19/00
CPCG16Z99/00
Inventor 苏光辉张亚培田文喜余红星秋穗正
Owner XI AN JIAOTONG UNIV
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