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Nuclear power plant internal originating event grouping method and device and nuclear power plant probability safety analysis method and device

A grouping method, the technology of nuclear power plants, applied in the field of nuclear power, can solve problems such as lack of implementation steps, analysis methods, low analysis quality, and affecting model calculation speed

Pending Publication Date: 2022-03-11
CHINA NUCLEAR POWER ENG CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

There are usually hundreds of initiating events in nuclear power plants. Building an analysis model one by one will bring a huge workload and seriously affect the calculation speed of the model. In the existing PSA standards at home and abroad (NB / T 20037.11-2018RK, ASME / ANS RA -Sb-2013, IAEA-SSG-3) all propose that initiating events should be merged and grouped, but these standards only give principled requirements and cannot be directly applied to actual work, which has led to the current development of PSA initiating events Event grouping is still mainly based on the experience and subjective judgment of analysts, lacking consistent implementation steps and analysis methods, and the analysis quality is not high

Method used

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  • Nuclear power plant internal originating event grouping method and device and nuclear power plant probability safety analysis method and device
  • Nuclear power plant internal originating event grouping method and device and nuclear power plant probability safety analysis method and device
  • Nuclear power plant internal originating event grouping method and device and nuclear power plant probability safety analysis method and device

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Embodiment 1

[0158] NB / T 20037.11-2018RK "Level 1 Probabilistic Safety Assessment Applied to Nuclear Power Plants Part 11 Power Operation Internal Events", see Table 1 for the requirements for merging internal initiating events. Among them: SR-IE-B1 is the purpose of merging (not specific technical requirements); SR-IE-B2 puts forward requirements, but does not give specific methods; SR-IE-B3 gives the basic principles of merging, but No more specific handling guidelines are given; SR-IE-B4 and SR-IE-B5 give handling principles for some specific situations.

[0159] The technical problems to be solved in the present invention include:

[0160] For SR-IE-B2, a structured analysis method is given;

[0161] For SR-IE-B3, specific processing guidelines are given;

[0162] For SR-IE-B4 and SR-IE-B5, specific processing guidelines are given.

[0163] Table 1 NB / T 20037.11-2018RK requirements for merging initiating events

[0164]

[0165] 1. Analysis process

[0166] figure 1 The overal...

Embodiment 2

[0259] Such as figure 2 As shown in the dashed box, this embodiment provides a device for grouping initiating events inside a nuclear power plant, including:

[0260] The acquisition module is used for initiating events of nuclear power plants to form an initiating event list,

[0261] The first judging module is used for judging whether the consequences of each initiating event in the initiating event list affect the mitigation capability of the multi-unit power plant,

[0262] The first receiving module is connected to the first judging module, and is used for receiving the initiating event as a separate group when the first judging module judges that the consequences of an initiating event affect the mitigation capability of a multi-unit power plant,

[0263] The second judging module is connected with the first judging module, and is used for judging whether the consequences of the initiating event affect the large release of radioactivity when the first judging module j...

Embodiment 3

[0317]The nuclear power plant probabilistic safety analysis method of this embodiment includes:

[0318] Adopt the internal initiating event grouping method of the nuclear power plant of embodiment 1 to carry out initiating event grouping, obtain a plurality of initiating event groups,

[0319] For multiple initiating event groups, the analysis models are constructed and simulated one by one to calculate the core damage frequency and radioactive mass release frequency corresponding to each initiating event group.

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Abstract

The invention provides a nuclear power plant internal originating event grouping method and device and a nuclear power plant probability safety analysis method and device.The grouping method comprises the steps that for each originating event in an originating event list, whether the consequence of the originating event affects the mitigation capacity or radioactive mass release of a multi-unit power plant or not is judged, and if yes, the originating events are independently listed into one group; if not, classifying the originating events into other originating event sets, classifying the originating events with consistent safety functions in the sets into one group, and for each originating event in each safety function consistent group, sequentially judging whether the originating events conform to the power plant response consistency criterion of each safety function in the group or not according to the sequence of the safety functions in the group; if yes, classifying the initial events into corresponding safety function groups in corresponding safety function consistent groups, if not, performing envelope grouping on the remaining initial events in each safety function consistent group, judging a first grouping result according to a quantitative result consistency criterion, and if not, performing splitting. According to the invention, the blank of starting event grouping is filled.

Description

technical field [0001] The invention relates to the field of nuclear power, in particular to a method and device for grouping initiating events inside a nuclear power plant, and a method and device for probabilistic safety analysis of a nuclear power plant. Background technique [0002] With the increase in the number of nuclear power units in operation in China, the safe operation of nuclear power units has attracted increasing attention. At present, Probabilistic Safety Assessment (PSA) technology is widely used at home and abroad to assess the risk of nuclear accidents in nuclear power plants. The basic principle of PSA technology is to identify all initiating events that may affect the safe operation of nuclear power units, analyze the response process of the nuclear power plant in various initiating events, consider the system failures involved, personnel intervention failures, etc., and construct a comprehensive The core damage and large radioactive release logic mode...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06Q10/06G06Q50/06G06F30/20G06F111/08G06F119/02
CPCG06Q10/0635G06Q50/06G06F30/20G06F2111/08G06F2119/02
Inventor 杨健马超邓伟冯楚然
Owner CHINA NUCLEAR POWER ENG CO LTD