Nuclear power plant integrated in-core instrumentation assembly

Abstract

The invention discloses a nuclear power plant integrated in-core instrumentation assembly. The in-core instrumentation assembly introduces an in-core from a top cover of a reactor pressure vessel, and comprises an upper shell located outside the reactor pressure vessel, a shell located inside the reactor pressure vessel, a plurality of neutron fluence rate measurers used for detecting axial power distribution of the in-core and a thermocouple used for measuring outlet temperature of the in-core; the neutron fluence rate measurers and the thermocouple are all mounted in the shell, and the shell is used for ensuring that the neutron fluence rate measurers and the thermocouple are not in contact with a primary circuit coolant. Compared with the prior art, the nuclear power plant integrated in-core instrumentation assembly provided by the invention introduces the in-core from the top cover of the reactor pressure vessel, and meets the design requirements of advanced reactors; moreover, simultaneous measurement on the outlet temperature of the in-core and the neutron fluence rate of the in-core can be realized, and the trepanning amount of the reactor pressure vessel is reduced, so that the design safety of the reactors can be improved.

Description

technical field [0001] The invention belongs to the field of nuclear power plant core measurement, and more specifically, the invention relates to an integrated nuclear power plant core measurement component. Background technique [0002] Nuclear power plant reactors are equipped with core measuring instruments for measuring core outlet temperature and core neutron flux rate. In known nuclear power plants, the core outlet temperature and the core neutron fluence rate are measured using different types of instrument assemblies. Specifically: the core outlet temperature is measured by 40 thermocouples arranged in the core fuel assembly, the thermocouples are divided into four groups, and the reactor pressure vessel is led out of the reactor pressure vessel through four thermocouple column assemblies; the neutron fluence rate of the core is The measurement is carried out through a finger sleeve equipped with a miniature fission chamber. The insertion end of the finger sleeve i...

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Problems solved by technology

[0003] However, the above-mentioned measurement method has at least the following defects: first, the core outlet temperature and the neutron flux rate of the core are measured separately using different instrument components, which increases the number of openings in the lower head of the reactor pressure vessel, resulting in a The stiffness of the head is reduced, which leads to a decrease in the safety of the reactor design; secondly, the finger sleeve used to measure the neutron flux rate of the reactor core is introduced from the l

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