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Method for calculating nuclide accumulated activity of secondary circuit system and equipment of nuclear power plant

A technology of cumulative activity and calculation method, applied in the direction of calculation, nuclear power generation, design optimization/simulation, etc., can solve problems such as the migration and accumulation of nuclides that cannot be calculated well, and achieve the effect of convenient calculation of specific activity

Active Publication Date: 2022-05-27
HARBIN ENG UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] At the problems referred to above, the object of the present invention is to propose a kind of calculation method of nuclear power plant secondary circuit system and equipment nuclide accumulation activity, the calculation method of this kind nuclear power plant secondary circuit system and equipment nuclide accumulation activity, can well Calculate the cumulative activity of radioactive substances in the secondary circuit equipment of the nuclear power plant after the steam generator heat transfer tube rupture accident, and solve the problem that the migration and accumulation of nuclides in the secondary circuit equipment cannot be well calculated in the prior art

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  • Method for calculating nuclide accumulated activity of secondary circuit system and equipment of nuclear power plant
  • Method for calculating nuclide accumulated activity of secondary circuit system and equipment of nuclear power plant
  • Method for calculating nuclide accumulated activity of secondary circuit system and equipment of nuclear power plant

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Embodiment 1

[0040] according to figure 1 As shown, this embodiment proposes a method for calculating the cumulative activity of nuclides in the secondary circuit system and equipment of a nuclear power plant, including the following steps:

[0041] Step 1: Determine the type of radionuclide i released by the rupture of the heat transfer tube of the steam generator, and obtain the mass C of the radionuclide i released from the primary circuit to the secondary circuit of the nuclear power plant per unit time i and state, the state and quality of real-time release of radionuclide i can be reasonably simplified through the SGTR release source term provided by the nuclear power plant and combined with the nature of the flow network;

[0042] Step 2: According to the type of secondary circuit equipment, the flow in and out of each branch, and the actual physical parameters, the nodes of the secondary circuit fluid network are divided, and the unstructured node division method is adopted to redu...

Embodiment 2

[0075] according to figure 2 As shown, this embodiment provides a method for calculating the cumulative activity of nuclides in the secondary circuit system and equipment of a nuclear power plant, including the following steps:

[0076] Step 1: Based on the release source term of the SGTR accident, obtain the mass C of the nuclide i released from the primary circuit to the secondary circuit of the nuclear power plant per unit time i and state, the state of nuclide i in this step refers to whether the nuclide is distributed in gaseous or liquid state, since the calculation method needs to consider the deposition process and leakage process of nuclide i, the state of the nuclide source term needs to be clarified in order to simplify the deposition and For the leakage equation, the state and mass of the real-time release of radionuclide i can be reasonably simplified through the SGTR release source term provided by the nuclear power plant and combined with the properties of the ...

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Abstract

The invention provides a nuclear power plant secondary circuit system and equipment nuclide cumulative activity calculation method, which comprises the steps of obtaining the mass Ci and the state of nuclide i released from a primary circuit of a nuclear power plant to a secondary circuit in unit time, dividing secondary circuit fluid network nodes, obtaining position nodes of leaked air according to a secondary circuit fluid network, and calculating the nuclide cumulative activity of the nuclear power plant secondary circuit system and equipment. The method comprises the following six steps: calculating a leakage coefficient of radionuclide i, then calculating deposition efficiency of the radionuclide i in each device, then establishing an accumulated mass balance equation of the radionuclide i of each device, and finally performing device accumulated specific activity conversion by considering a gas-liquid distribution problem of suspended nuclide. The method is suitable for building the cumulative activity model of each device of the whole secondary circuit device flow net, the balance equation is divided according to the nuclide substance state, the influence of deposition, decay and leakage is fully considered, gas-liquid distribution in the node is carried out on the suspended radioactive substance by means of the quantity of the radioactive substance and physical property parameters in the node, and the gas-liquid distribution efficiency is improved. Therefore, the specific activity is convenient to calculate.

Description

technical field [0001] The invention relates to the technical field of nuclear reactor engineering, in particular to a method for calculating the cumulative activity of nuclides in a secondary circuit system of a nuclear power plant and equipment. Background technique [0002] The steam generator is the core component of heat transfer in the reactor system, and also an important component of the pressure boundary of the reactor primary loop system, which plays an important role in the isolation of the primary loop radioactivity. Due to the large temperature difference and pressure difference on both sides of the heat exchange tube of the steam generator, there is a large mechanical stress and thermal stress. At the same time, the high-speed flow of the primary and secondary circuit fluids will cause vibration and corrosion, and the heat transfer tube is prone to occur. The rupture leads to the leakage of the primary circuit coolant to the secondary circuit, and the radioacti...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/28G06F30/18G06F17/11G06F17/18G06F113/08
CPCG06F30/28G06F30/18G06F17/11G06F17/18G06F2113/08Y02E30/30
Inventor 夏庚磊鲜磊彭敏俊赵强孙觊琳王航张博文王晨阳
Owner HARBIN ENG UNIV