Control rod distribution structure of 177 reactor core

Abstract

The invention discloses a control rod distribution structure of a 177 reactor core. The control rod distribution structure comprises 61 bundles of control rods, wherein the 61 bundles of control rods are divided into 8 groups, namely a group R, a group G1, a group G2, a group N1, a group N2, a group SA, a group SB and a group SC; the group R comprises temperature adjusting rods; the group G1, the group G2, the group N1 and the group N2 comprise power compensation rods; the group SA, the group SB and the group SC comprise shutdown rods; each of the group G1 and the group G2 is composed of grey body control rods; and the other groups are composed of black body control rods. According to the control rod distribution structure, the quantities of the temperature adjusting rods, the power compensation rods and the shutdown rods are set, the temperature adjusting rods, the power compensation rods and the shutdown rods are reasonably grouped, and space positions of all the control rods are optimized, so that an enough shutdown allowance is provided for the 177 reactor core by adopting the 61 bundles of control rods under the condition that holes in a top cover of a pressure container are not increased; and the shutdown allowance meets the safety requirements of annual reloading and 18-month reloading.

Description

technical field [0001] The invention relates to the field of pressurized water reactor nuclear power plant reactors, in particular to the distribution of control rods in the reactor core. Background technique [0002] Fuel assemblies are an important part of the core of a nuclear reactor. Nuclear reactor core design is one of the key design contents of nuclear power plants. The main task of nuclear reactor core design is to provide a nuclear reactor core that meets the overall design requirements of a pressurized water reactor nuclear power plant from the perspective of nuclear reactor physics, including determining the number of fuel assemblies and the arrangement of fuel assemblies in the nuclear reactor core. [0003] The core of the conventional mega-kilowatt three-loop pressurized water reactor nuclear power plant is composed of 157 fuel assemblies, and its core power density is relatively high, and its thermal safety margin is relatively low. [0004] In order to sol...

AI Technical Summary

Problems solved by technology

[0005] However, compared with the 157 core, the 177 core has increased the number of fuel assemblies. If the same control rod distribution strategy as the 157 core is adopted, the reactivity control capability is insufficient and cannot provide enough shutdown margin to ensure safety.

If the number of control rods is increased, the number of openings on the top cover of the pressure vessel will inevitably increase, which will affect the reliability of the pressure vessel structure

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