Nuclear fuel circulation facility UF6 accident leakage consequence evaluation and calculation method

A calculation method and nuclear fuel technology, applied in the direction of calculation, data processing applications, instruments, etc., can solve problems that do not conform to the diffusion process, uncertainty, inconvenient calculation of accident consequences, etc.

Active Publication Date: 2019-10-29
CHINA INST FOR RADIATION PROTECTION
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Problems solved by technology

[0008] 1) For the accident source item, the parameters of the source item are directly set according to the accident scene, resulting in great uncertainty in the calculation of leakage consequences;
[0009] 2) In the diffusion calculation, the traditional Gaussian model is used to calculate the diffusion after the heavy gas characteristics are calculated, and the gravi

Method used

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  • Nuclear fuel circulation facility UF6 accident leakage consequence evaluation and calculation method
  • Nuclear fuel circulation facility UF6 accident leakage consequence evaluation and calculation method
  • Nuclear fuel circulation facility UF6 accident leakage consequence evaluation and calculation method

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Embodiment Construction

[0243] Exemplary inventive nuclear fuel cycle facility UF 6 The flow of the calculation method for accident leakage consequence assessment is as follows: Figure 1-4 As shown, the specific implementation process is as follows:

[0244] (1) Calculation and determination of source item parameters

[0245] According to the actual working conditions, the source parameter calculation scenario includes three accident scenarios, which are UF 6 Liquid Sustained Release, UF 6 Continuous release of gas, large amount of UF 6 The liquid is released instantaneously. The input conditions of the calculation model are the actual working conditions (actual accident conditions), including container temperature, pressure, loading capacity and damage size; the output parameters are source term characteristics, including release rate (leakage rate), puff two-phase fraction, smoke Puff density and puff temperature.

[0246] 1. UF 6 Calculation and determination of source term parameters when l...

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Abstract

The invention belongs to the technical field of nuclear safety evaluation, and relates to a nuclear fuel circulation facility UF6 accident leakage consequence evaluation and calculation method. The evaluation calculation method sequentially comprises the following steps: (1) determining source item parameters: calculating the source item parameters according to actual working conditions, or knowing or assuming the source item parameters; (2) carrying out diffusion calculation in the atmospheric environment under different accident scenes according to the source item parameters determined in the step (1); and (3) calculating the UF6 accident consequence health effect. By utilizing the evaluation calculation method, the accident leakage consequence evaluation calculation exclusive to UF6 canbe simply and quickly carried out, and the calculation result is more definite and reliable.

Description

technical field [0001] The invention belongs to the technical field of nuclear safety evaluation and relates to a nuclear fuel cycle facility UF 6 Calculation method for accident leakage consequence assessment. Background technique [0002] involving UF 6 The nuclear fuel cycle facilities leaked by the accident include uranium conversion plants, fuel assembly plants, uranium enrichment plants and depleted uranium storage sites. During the operation of the above-mentioned nuclear fuel cycle facilities, UF may occur due to equipment failure or operational errors. 6 Accidental release of (possibly a nuclear fuel cycle facility such as a uranium enrichment plant pipe rupture releasing UF 6 High-temperature gas, or the rupture of the pressure tank releases UF 6 The liquid, long-term storage of depleted uranium also has DUF caused by container damage 6 risk of leakage), UF after leakage 6 Immediately react with moisture in the environment to form UO 2 f 2 and HF. Soluble ...

Claims

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Application Information

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IPC IPC(8): G06Q10/06
CPCG06Q10/0639G16C20/10
Inventor 崔慧玲姚仁太辛存田张新骞张芳
Owner CHINA INST FOR RADIATION PROTECTION
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