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A Method Applicable to Dose Risk Control of High-Temperature Gas-cooled Reactor Nuclear Power Plant Clusters

A high-temperature gas-cooled reactor, risk control technology, applied in data processing applications, instruments, calculations, etc., can solve problems such as no dose risk control, risk management, etc.

Active Publication Date: 2021-05-04
HUANENG SHANDONG SHIDAOBAY NUCLEAR POWER CO LTD +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, at present, this indicator is only used as a reference value for the radiation dose of residents after the accident.
PSA technology helps nuclear power plants to predict dose risk during operation activities, but there is no method for dose risk control
Due to the inherent safety of high-temperature gas-cooled reactors, traditional PSA risk indicators such as core damage frequency and early large-scale release frequency cannot be used for its risk management. Dose risk is used as its risk margin to establish a certain dose risk control method It is of great significance to its operation safety management

Method used

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  • A Method Applicable to Dose Risk Control of High-Temperature Gas-cooled Reactor Nuclear Power Plant Clusters
  • A Method Applicable to Dose Risk Control of High-Temperature Gas-cooled Reactor Nuclear Power Plant Clusters
  • A Method Applicable to Dose Risk Control of High-Temperature Gas-cooled Reactor Nuclear Power Plant Clusters

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Embodiment Construction

[0023] The present invention will be described in detail below in conjunction with specific embodiments.

[0024] The method of the present invention applicable to the dose risk control of high temperature gas-cooled reactor nuclear power plant groups comprises the following steps:

[0025] Step 1: Assuming that there are N reactors in the high temperature gas-cooled reactor nuclear power plant, and the i-th reactor needs to be temporarily changed, by running the PSA model and data, calculate the release frequency of various release types under the i-th reactor’s proposed configuration change , where configuration refers to the specific state of the unit composed of the specific conditions of the various systems and equipment of the nuclear power plant, which includes elements such as: unit operating mode, equipment standby / running status, unavailable equipment, tests, and external factors (such as high temperature weather, typhoon), etc. When the system configuration or equi...

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Abstract

The invention belongs to the technical field of safe operation of nuclear power plant units, and specifically relates to a method suitable for group reactor dose risk control in high-temperature gas-cooled reactor nuclear power plants. It includes the following steps: Suppose there are N reactors in a high-temperature gas-cooled reactor nuclear power plant, and the i-th reactor needs to be temporarily changed. By running the PSA model and data, calculate the releases of various release categories under the proposed change configuration of the i-th reactor. Frequency; note T as the time the power plant stays in this configuration, then the maximum dose risk of the high-temperature gas-cooled reactor nuclear power plant in this configuration is the cumulative individual dose risk at the plant boundary for a rolling 12 months before the proposed configuration change is calculated. D 0 , unit mSv; using the actual average exposure level of domestic public individuals of 0.1mSv / a as the limit, the maximum dose risk R generated by this change MAX ≤0.1‑D 0 , that is, the dose brought by the change cannot make the individual annual cumulative dose at the plant site boundary greater than the domestic average. The present invention provides a method basis for risk guidance decision-making for temporary changes in high-temperature gas-cooled reactors.

Description

Technical field [0001] The invention belongs to the technical field of safe operation of nuclear power plant units, and specifically relates to a method suitable for group reactor dose risk control in high-temperature gas-cooled reactor nuclear power plants. Background technique [0002] The particularity of the risks associated with nuclear power lies in its radioactive release. The effects of radioactive substances on humans can be divided into early health effects and delayed health effects. After a serious accident at a nuclear power plant, usually only those residents who are directly exposed to external exposure from radioactive smoke clouds and radioactive materials deposited on the ground, that is, who have received larger doses, will show early effects. Slow-onset health effects are random effects. Residents who did not die after being exposed to acute exposure, or received a dose that was too small to cause early death, or residents who were not exposed to acute e...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06Q10/06G06Q50/06
CPCG06Q10/0635G06Q50/06
Inventor 龚兵吴静陈永行王庆武陈选相
Owner HUANENG SHANDONG SHIDAOBAY NUCLEAR POWER CO LTD
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