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Proportion analysis method for heat removal process of passive nuclear power plant containment vessel system

A proportional analysis and containment technology, which is applied in nuclear engineering, nuclear power generation, nuclear reactor monitoring, etc., can solve the problem of the lack of heat removal capacity of the heat sink

Active Publication Date: 2013-12-11
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD +1
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  • Abstract
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  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

According to the investigation of the existing literature, the current PCS research is mostly focused on the analysis of the pressure response of the containment after the DBA accident, and the specific heat sink and PCS phenomenon are taken as the research objects, and the research on the heat removal capacity of the specific heat sink is intuitively quantified. hardly

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  • Proportion analysis method for heat removal process of passive nuclear power plant containment vessel system
  • Proportion analysis method for heat removal process of passive nuclear power plant containment vessel system
  • Proportion analysis method for heat removal process of passive nuclear power plant containment vessel system

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Embodiment Construction

[0101] Such as figure 1 As shown, a schematic diagram of the PCS heat removal process after a hypothetical DBA accident occurs in the passive nuclear power plant containment system of the present invention is given. When a hypothetical large breach loss-of-water accident (LOCA) or main steam line break accident (MSLB) occurs in the containment system of a passive nuclear power plant, high-temperature, high-pressure fluid is released from the breach 101 into the gas phase space 102 of the containment. The gas phase space 102 stores mass and energy, and the pressure of the containment vessel rises rapidly. When the containment pressure reaches the set value and the PCS is put into operation after an appropriate time delay, the water flows out from the PCCWST water tank (not shown in the figure) to the outer wall of the steel containment 103, and most of the outer wall of the steel containment 103 will cover a layer of water film. In the gas phase space 102 of the containment, ...

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Abstract

The invention discloses a proportion analysis method for a heat removal process of a passive nuclear power plant containment vessel system. The proportion analysis method comprises the following steps: (1) dividing the containment vessel system into a crevasse heat source, a containment vessel internal gas-phase space heat trap, an inner solid heat trap, a steel vessel heat trap, a diversion plate heat trap and a shielding factory heat trap; and (2) analyzing heat and mass transfer processes of the crevasse heat source, the containment vessel internal gas-phase space heat trap, the inner solid heat trap, the steel vessel heat trap, the diversion plate heat trap and the shielding factory heat trap, and calculating a transmission quality proportion group and an energy proportion group of each component. The proportion analysis method is suitable for proportion analysis of the heat removal process of the passive nuclear power plant containment vessel system such as AP600, AP1000 and CAP1400 and can be used for evaluating the contribution made by various heat and mass transfer processes at any time to the heat removal capacity of the containment vessel system.

Description

technical field [0001] The invention relates to the field of nuclear power plant containment response analysis, in particular to a proportional analysis method for the heat removal process of a passive nuclear power plant containment system. Background technique [0002] The safety and reliability of nuclear power plants are very important. The containment vessel and its support system are the physical barrier between the reactor and the environment. It plays a role in preventing or mitigating the release of radioactive substances to the environment in case of an accident. [0003] The Passive Containment Cooling System (PCS) is an important part of the third-generation large-scale advanced pressurized water reactor—the passive safety system, and it is also one of the important technical features of the advanced pressurized water reactor. PCS is used to remove heat from the containment, and its essential feature is that it relies only on gravity and natural circulation, comb...

Claims

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Application Information

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IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 王国栋张迪王喆张经瑜汤微建杨杏波许志红
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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