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A method for calculating source term model of site selection of advanced small nuclear reactor power plant

A nuclear reactor and model calculation technology, applied in calculation, electrical digital data processing, design optimization/simulation, etc., can solve problems that cannot reflect well, do not consider radioactive material settlement, retention, etc.

Active Publication Date: 2019-02-15
CHINA POWER INVESTMENT POWER ENG CO LTD
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Problems solved by technology

[0023] The traditional model does not consider the settlement and retention of radioactive materials in the auxiliary factory building or the ground factory building. When using this model to calculate the source item, engineering often divides it by a coefficient to consider the retention effect of the auxiliary factory building on radioactive materials. Conservative estimates based on experience do not reflect the real situation very well

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  • A method for calculating source term model of site selection of advanced small nuclear reactor power plant
  • A method for calculating source term model of site selection of advanced small nuclear reactor power plant
  • A method for calculating source term model of site selection of advanced small nuclear reactor power plant

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Embodiment Construction

[0039] In order to make the present invention more comprehensible, preferred embodiments are described in detail below with accompanying drawings.

[0040] The calculation method for the site selection source term model of an advanced small nuclear reactor power plant provided by the present invention still follows the assumptions of RG1.183 on the amount and time period of radioactive release, and considers the influence of above-ground-underground arrangement and an additional layer of release barrier. to combine image 3 , the present invention specifically comprises the following steps:

[0041] Step 1. Establish the radioactivity A leaked from the containment into the environment 0 The calculation equation:

[0042]

[0043] In formula (2-1), Q is the release rate of radioactivity from the reactor to the containment atmosphere after the accident, λ is the decay constant, t is the calculation time step, L 1 is the leakage rate from the containment to the cavity, D 0...

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Abstract

A method for calculating source term model of site selection of advanced small nuclear reactor power plant is characterized by comprising the following steps of establishing a calculation equation ofthe radioactivity A0 leaking into environment through a containment shell; establishing the variation equation of radioactivity A1 in cavity locate on ground, and establishing the equation of leakage-induced environmental radioactivity A2; simultaneously linking the above equation to obtain an improved source term model of advanced small reactor site selection. The model obtained by the improved method of the invention takes into account the characteristics of the above-ground arrangement, namely, not only takes into account the blocking and retaining effects of the underground containment shell on radioactivity, but also takes into account the blocking and retaining effect of the ground workshop. The disappearance of radioactivity is described in detail by leakage, removal, and decay coefficients. Compared with the traditional source term model, the method is more precise and close to the layout characteristics of the advanced heap.

Description

technical field [0001] The invention relates to a site selection source term model calculation method suitable for site selection of small nuclear reactor power plants, which can be used for site selection of advanced small nuclear reactor power plants. Background technique [0002] In the previous calculation models of siting source terms, it was mainly for large pressurized water reactors, and large pressurized water reactors were arranged on the ground. The newly developed small reactor nuclear power plants, such as mPower, Nuscale, ACP100, etc., have chosen the design of placing the reactor below the ground, so that compared with the large reactor, the small pressurized water reactor has an additional safety barrier, such as figure 1 shown. [0003] The source item model of traditional PWR siting is introduced as follows: [0004] According to the requirements of GB6249, in the site selection stage, the site selection source item should consider the melting of the whol...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F17/50
CPCG06F30/20
Inventor 胡雨刘晓壮李海钰郭峰赵华阳郑勇
Owner CHINA POWER INVESTMENT POWER ENG CO LTD
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