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18-month refueling loading method for pressurized water reactor first-cycle boracic core

A first cycle, pressurized water reactor technology, which is applied in the field of 18-month refueling and loading of boron-containing cores in the first cycle of pressurized water reactors, can solve the problems of short refueling cycle in the first cycle, etc., and can reduce the concentration of components. Effects of differentiation, high economy and operational flexibility, high safety

Active Publication Date: 2018-03-30
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] The purpose of the present invention is to provide a 18-month refueling loading method for the first cycle boron-containing core of a pressurized water reactor, which solves the short problem of the first cycle refueling period caused by the existing loading method, and can be achieved by the loading method of the present invention. Fast and easy to achieve the goal of 18-month long-term refueling in the first cycle

Method used

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  • 18-month refueling loading method for pressurized water reactor first-cycle boracic core

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Embodiment 1

[0025] Such as figure 1 As shown, an 18-month refueling and loading method for the first-cycle boron-containing core of a PWR. The PWR core is composed of 121 groups of AFA3G fuel assemblies. The diameter is 267.0cm, and the aspect ratio is 1.37. Each AFA 3G fuel assembly consists of 264 fuel rods, 24 zirconium alloy guide tubes and a zirconium alloy gauge tube arranged in a 17×17 square array.

[0026] The first cycle core loading is divided into 4 zones according to the U-235 enrichment degree, and the fuel assemblies with 4 different U-235 enrichment degrees are used, which can better flatten the core power distribution compared with the 3 enrichment degrees ; The U-235 enrichment degrees in Zone 4 are 1.9%, 2.6%, 3.1% and 3.7%, respectively, and the number of fuel assemblies are 21, 32, 44 and 24 groups respectively. Considering that all the fuel assemblies used in the first cycle are new fuel assemblies, In order to effectively flatten the power distribution of the core...

Embodiment 2

[0039] This embodiment is based on Example 1, and the number of boron glass rods of the component with an enrichment degree of 2.6% in the embodiment is replaced by 4, or 8 or 20, and the boron glass rods of the component with an enrichment degree of 3.1% The number of glass rods is replaced by 8, or 4 or 24.

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Abstract

The invention discloses an 18-month refueling loading method for a pressurized water reactor first-cycle boracic core. The pressurized water reactor first-cycle boracic core is composed of 121 sets offuel assemblies. The first cycle fuel assembly is divided into four regions according to the U-235 enrichment degrees, the U-235 enrichment degrees of the four regions are 1.9%, 2.6%, 3.1% and 3.7% respectively, the fuel assemblies are the sets 21, 32, 44 and 24, the first cycle core adopts the high-leakage loading mode, and solid burnable poison adopted by the first cycle core is borosilicate glass rods; the problem that due to three-region arrangement, a nuclear enthalpy rise factor meeting the requirement is hard to obtain is solved, the technical requirement for the first-cycle 18-month long-period refueling design is met while it is ensured that a reactor has the high safety, and the cycle length is prolonged to 473 effective full power days from annual refueling 387 effective full power days.

Description

technical field [0001] The invention relates to the technical field of pressurized water reactor core refueling, in particular to an 18-month refueling and loading method for the first cycle boron-containing core of a pressurized water reactor. Background technique [0002] PWR core fuel management generally refers to the determination of the enrichment of fuel used in the core, the concentration of burnable poisons, and The type and arrangement of various components and poisons in the core, etc., make the design results of the reactor core meet the nuclear design criteria and the overall requirements of the power plant. The quality of core fuel management directly affects the economy and safety of nuclear power plants, and is the basis for subsequent safety analysis or evaluation. [0003] At present, the traditional method of loading the first cycle core of the domestic 600,000-kilowatt pressurized water reactor nuclear power plant is mainly the annual refueling loading m...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/20
CPCG21C19/205Y02E30/30
Inventor 李庆吉文浩陈亮李向阳强胜龙刘同先谢运利刘晓黎陈长于颖锐李天涯宫兆虎蒋朱敏肖鹏
Owner NUCLEAR POWER INSTITUTE OF CHINA
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