Fast reactor core online monitoring method and system

Abstract

The invention relates to a fast reactor core online supervision method and system. The method comprises the steps that firstly, a fast reactor outer nuclear measurement system and a control rod monitoring system are used to obtain monitoring data of reactor nuclear power and the position in a control rod reactor; the real-time reactor power and in-reactor control rod position measurement data obtained in the previous step are taken as real-time input parameters of a reactor core neutronics calculation program in a selected time step, steady-state reactor core calculation is carried out to obtain in-reactor neutron flux density and power, further calculation is carried out to obtain assembly burn-up data, and the data is stored in a database; and related data of the database is extracted asrequired for graphical display. According to the invention, online supervision of a fast reactor core can be realized, detailed data support is provided for operation decision and fuel management ofa fast reactor power plant, and the economic benefit and the safety level of the power plant are improved.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor design, and in particular relates to a fast reactor core online monitoring method and system. Background technique [0002] In order to ensure the safe use of nuclear fuel in the nuclear power plant reactor, some parameters of the reactor and related parameters of the core measurement system should be monitored online, and the operation trend of the relevant content should be tracked and analyzed to guide the operation and ensure that the reactor operating parameters meet the design. Require. At present, the mainstream pressurized water reactor nuclear power plants are equipped with core supervision and management. [0003] Fast neutron reactor (fast reactor) is the main reactor type of the fourth-generation nuclear energy system, and the technology with the highest level of technical maturity is the sodium-cooled fast reactor technology that uses liquid metal sodium as the coolant. So f...

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Problems solved by technology

[0005] Fuel assembly and reactor system designs in fast reactors are quite different from thermal neutron reactors such as pressurized water reactors, for example: fuel assemblies usually use a tight grid and are usually designed with assembly outer casings, coolant operating temperatures are high, primary loops The integrated design of the system pool, etc. make it impossible to arrange detectors in the core fuel assembly in the fast reactor core to measure the neutron flux density or power of each fuel assembly

Operators cannot directly monitor or obtain parameters such as fuel assembly power, neutron flux density, power peak, and fuel assembly burnup through in-core detectors online

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