MOX fuel rod, MOX fuel assembly and method for flattening axial power

A fuel rod and fuel technology, applied in the field of nuclear engineering, can solve the problems of reducing the fuel consumption at both ends of the fuel rod, flattening the axial power of a single fuel rod, and uneven reactor power, so as to reduce the fission reaction rate and reduce Low cost and difficulty, the effect of enhancing the safety of the core

Inactive Publication Date: 2018-09-18
SUN YAT SEN UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, this study only aimed at flattening the radial power of the MOX fuel assembly as a whole, and did not specifically involve how to flatten the axial power of a single fuel rod
However, due to the uneven axial power of a single fuel rod, the reactor power will be uneven, thereby reducing the fuel consumption at both ends of the fuel rod and affecting the efficiency of the reactor operation

Method used

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  • MOX fuel rod, MOX fuel assembly and method for flattening axial power
  • MOX fuel rod, MOX fuel assembly and method for flattening axial power
  • MOX fuel rod, MOX fuel assembly and method for flattening axial power

Examples

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Embodiment 1

[0035] see figure 1 , which is a schematic diagram of the doped fuel position of the MOX fuel rod in this embodiment. In this embodiment, the MOX fuel rod contains one-ninth axially doped fuel. Specifically, the MOX fuel rod is divided into 9 sections from top to bottom, and the doped fuel B is distributed in the fifth section, located in the axial middle of the MOX fuel rod, and the rest of the section is normal fuel A. According to the distribution of the actual moderator temperature, the doping position should be lower.

Embodiment 2

[0037] see figure 2 , which is a schematic diagram of the doped fuel position of the MOX fuel rod in this embodiment. In this embodiment, the MOX fuel rod contains two-ninths of the axially doped fuel. Specifically, the MOX fuel rod is divided into 9 sections on average from top to bottom, and the doped fuel B is distributed in the fourth And the 6th section, with the center of the MOX fuel rod as the center axially symmetrical distribution, the remaining sections are normal fuel A. According to the distribution of the actual moderator temperature, the doping position should be lower.

Embodiment 3

[0039] see image 3 , which is a schematic diagram of the doped fuel position of the MOX fuel rod in this embodiment. In this embodiment, the MOX fuel rod contains three-ninths of the axially doped fuel. Specifically, the MOX fuel rod is divided into 9 segments on average from top to bottom, and the doped fuel B is distributed in the third , Sections 5 and 7 are axially symmetrically distributed around the center of the MOX fuel rod, and the remaining sections are normal fuel A. According to the distribution of the actual moderator temperature, the doping position should be lower.

[0040] Through the doping methods shown in Examples 1-3, the fuel at the axially high power position in the MOX fuel rod is set as the doped fuel, so as to flatten the axial power of the MOX fuel rod. The doped MOX fuel rods can form a MOX fuel assembly, specifically, the doped MOX fuel rods can be arranged with guide tube arrays to form a MOX fuel assembly for transmutation, and realize the axia...

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Abstract

The invention relates to an MOX fuel rod, an MOX fuel assembly and a method of flattening the axial power. The MOX fuel rod includes a doped fuel, the doped fuel is distributed in the axially middle part of the MOX fuel rod, and the doped fuel is a fuel doped with a long-lived minor actinide. The fuel in the axially middle part of the MOX fuel rod is the doped fuel, and the long-lived minor actinide in the doped fuel is transmuted in a neutron field to form a short-lived or stable nuclide, so the cost and the difficulty of final treatment of a spent fuel are reduced, and the treatment problemof the long-lived minor actinide in the spent fuel solved; and the transmutation of the long-lived minor actinide in the doped fuel, absorbing neutrons in the neutron field, is used to reduce the fission reaction rate of the doped fuel in order to reduce the original axial power and fuel consumption in the MOX fuel rod and the power and fuel consumption at a high combustion position, so the purposes of flattening the axial power of the MOX fuel rod, enhancing the reactor core safety and improving the fuel utilization rate are achieved.

Description

technical field [0001] The invention relates to the technical field of nuclear engineering, in particular to a MOX fuel rod and a MOX fuel assembly with the functions of transmuting minor actinide nuclides and flattening axial power. Background technique [0002] With the rapid growth of our country's economy, the demand for energy has greatly increased, especially after the signing of the Paris Agreement, the development of green energy has become a top priority. Nuclear energy is characterized by high efficiency, cleanliness and stability, which meets my country's energy needs. In recent years, my country's pressurized water reactor nuclear power plants have grown rapidly, but the accumulation of spent fuel has also increased rapidly. These spent fuels have a long lifespan and high radiotoxicity, threatening the human living environment for a long time. [0003] Spent fuel disposal issues, especially minor actinide nuclides with long half-lives in spent fuel 237 Np, 24...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/26G21C3/30
CPCG21C3/26G21C3/30Y02E30/30
Inventor 袁岑溪陈胜利
Owner SUN YAT SEN UNIV
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