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
- Summary
- Abstract
- Description
- Claims
- Application Information
AI Technical Summary
Problems solved by technology
Method used
Image
Examples
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 ...
PUM
Login to View More Abstract
Description
Claims
Application Information
Login to View More 


