System and method for online monitoring of integrity of lead-bismuth reactor fuel element can

A fuel element and monitoring system technology, which is applied in the field of reactor leakage monitoring, can solve problems such as the inability to realize continuous monitoring and non-mechanism of diagnostic conclusions, and achieve the effect of realizing automation and real-time and improving reliability

Inactive Publication Date: 2018-08-10
CHINA NUCLEAR POWER TECH RES INST CO LTD +3
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Problems solved by technology

[0013] The technical problem to be solved by the present invention is to provide an online monitoring system and method for the integrity of the cladding of lead-bismuth stack fuel elements, which can improve the problem that the existing monitoring system or method cannot realize continuous monitoring and the diagnosis conclusion is non-mechanistic

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  • System and method for online monitoring of integrity of lead-bismuth reactor fuel element can
  • System and method for online monitoring of integrity of lead-bismuth reactor fuel element can

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Embodiment Construction

[0042] The following descriptions of various embodiments refer to the accompanying drawings to illustrate specific embodiments in which the present invention can be implemented.

[0043] An embodiment of the present invention provides an online monitoring system for the cladding integrity of lead-bismuth reactor fuel elements, which is used for monitoring accelerator-driven subcritical fast neutron reactors. This embodiment takes the monitoring of an accelerator-driven subcritical fast neutron reactor by using the online monitoring system as an example to further illustrate the function and working mode of the system. The accelerator-driven subcritical fast neutron reactor uses lead-bismuth alloy as the coolant, and the primary coolant system is mainly composed of the main vessel, reactor internals, main pump, main heat exchanger and main pipe. Fuel components use 4.95% 235 U-enriched regular hexagonal component, cladding material type is 15-15 Ti, and the gap between fuel pe...

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Abstract

The invention provides a system for online monitoring of the integrity of a lead-bismuth reactor fuel element can. The system comprises a delayed fission neutron detection unit which is used for monitoring and acquiring data of a delayed fission neutron fluence rate in real time, a characteristic fission nuclide detection unit which is used for monitoring and acquiring data of characteristic fission nuclide radioactivity and a back-end data centralized processing unit, wherein the back-end data centralized processing unit has the functions of automatic alarm and output of an evaluation conclusion report, and is used for receiving the data of the delayed fission neutron fluence rate and the data of the characteristic fission nuclide radioactivity, comparing the data with preset corresponding thresholds, and giving a comparison conclusion. Through the online monitoring system, automatic and real-time evaluation of the integrity of the lead-bismuth reactor fuel is achieved, and the data is monitored and acquired through the delayed fission neutron detection unit and characteristic fission nuclide detection unit simultaneously, and is verified through the data centralized processing unit, so that the reliability of on-line integrity evaluation of the lead-bismuth fuel is improved greatly, and the system can also be used for guiding shutdown leakage tests.

Description

technical field [0001] The invention relates to the technical field of reactor leakage monitoring, in particular to an on-line monitoring system and method for the integrity of the fuel element cladding of a lead-bismuth reactor. Background technique [0002] Fuel element cladding is the second of the four safety barriers in nuclear power plants, and undertakes the task of containing the fission products of fuel pellets. If the fuel element cladding is damaged, the fission products will be released into the primary coolant through the breach, which will have a potential impact on the safe operation of the nuclear power plant. It is of great contribution to the safe and economical operation of nuclear power plants to timely and accurately determine whether the fuel element cladding is damaged, the size of the breakage and the location of the breakage during operation. After the fuel element cladding is damaged and the reactor is shut down, the fuel rod cladding must be leak ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00
CPCG21C17/002Y02E30/30
Inventor 林鹏刘春雨单陈瑜刘夏杰吕永红谢文章蒋丹枫林有奇周志伟
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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