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Thorium-base fuel assembly and small pressurized water reactor

A fuel assembly and fuel technology, applied in the field of nuclear reactors, can solve the problems that the core refueling cycle cannot reach 5-10 years, etc., and achieve the improvement of neutron economy and safety, strong reactivity control ability, and transformation ability improvement Effect

Active Publication Date: 2016-11-16
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a thorium-based fuel assembly with a refueling period of 5 to 10 years to solve the problem that the existing core refueling period cannot reach 5 to 10 years

Method used

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  • Thorium-base fuel assembly and small pressurized water reactor
  • Thorium-base fuel assembly and small pressurized water reactor
  • Thorium-base fuel assembly and small pressurized water reactor

Examples

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Effect test

Embodiment 1

[0031] Such as figure 1 As shown, a thorium-based fuel assembly includes 232 fuel rods 1 with a cladding thickness of 0.5 mm and an outer diameter of 9.1 mm, 57 guide tubes 2 with an outer diameter of 9.1 mm, fuel rods 1, and guide tubes 2 Arranged at intervals, the distance between adjacent fuel rods 1 is 1.0mm, the distance between adjacent fuel rods 1 and guide tube 2 is 1.0mm, and the distance between fuel assemblies is 172.7mm. 235 UO with 20% U abundance 2 fuel, UO 2 Fuel and ThO 2 The fuel ratio is 1:1, 235 U percentage content is 8.8%, 232 The Th content is 43.9%. The fuel rods 1 and guide tubes 2 are evenly arranged in a square grid to form a square fuel assembly 4 with a square assembly box 3 on the periphery.

[0032] Such as figure 2 As shown, a small pressurized water reactor adopts figure 1 The shown square fuel assembly 4 is structured as figure 2 In the shown core, a total of 57 boxes of fuel assemblies are arranged. The center distance of the fuel as...

Embodiment 2

[0035] This embodiment is based on embodiment 1, such as figure 1 As shown, a thorium-based fuel assembly includes 232 fuel rods 1 with a cladding thickness of 0.5 mm and an outer diameter of 9.0 mm, 57 guide tubes 2 with an outer diameter of 9.0 mm, fuel rods 1, and guide tubes 2 Arranged at intervals, the distance between adjacent fuel rods 1 is 1.0mm, the distance between adjacent fuel rods 1 and guide tube 2 is 1.0mm, and the distance between fuel assemblies is 172.7mm. 239 PuO with a Pu abundance of 18% 2 Fuel, PuO 2 Fuel and ThO 2 The fuel ratio is 1:1, 239 The total percentage of Pu is 8.8%, 232 The Th content is 43.9%. The fuel rods 1 and guide tubes 2 are evenly arranged in a square grid to form a square fuel assembly 4 with a square assembly box 3 on the periphery.

[0036] Such as figure 2 As shown, a small pressurized water reactor adopts figure 1 The shown square fuel assembly 4 is structured as figure 2 In the shown core, a total of 57 boxes of fuel as...

Embodiment 3

[0039] Such as image 3As shown, a thorium-based fuel assembly includes 270 fuel rods 1 with a cladding thickness of 0.5 mm and an outer diameter of 9.1 mm, 61 guide tubes 2 with an outer diameter of 9.1 mm, fuel rods 1, and guide tubes 2 Arranged at intervals, the distance between adjacent fuel rods 1 is 1.0mm, the distance between adjacent fuel rods 1 and guide tube 2 is 1.0mm, the distance between fuel assemblies is 186mm, and the abundance of 235U mixed in fuel pellets is 20% UO 2 fuel, UO 2 Fuel and ThO 2 The fuel ratio is 1:1, 235 U percentage content is 8.8%, 232 The Th content is 43.9%. The fuel rods 1 and guide tubes 2 are evenly arranged in a triangular grid to form a regular hexagonal fuel assembly 5 with a regular hexagonal assembly box on the periphery.

[0040] Such as Figure 4 As shown, a small pressurized water reactor adopts image 3 The shown regular hexagonal fuel assembly 5 is structured as Figure 4 In the shown core, a total of 55 boxes of fuel a...

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Abstract

The invention relates to a thorium-base fuel assembly and a small pressurized water reactor. A fuel core gives priority to thorium oxide (ThO2) and is mixed with UO2 fuel of which the 235U abundance is about 20% or PuO2 fuel of which the 239Pu abundance is about 18%. Fuel rods adopt a dense lattice arrangement way, an interval between the fuel rods is about 1.0mm, the fuel rods are arranged in a square or triangular lattice, and a square or a hexagonal fuel assembly is formed by an assembly box. A reactor adopts a periodic operation mode, i.e., the reactor operates for multiple days at each power, and outage is carried out for 30 days or more. The thorium-base fuel assembly and the small pressurized water reactor which are provided by the invention have high reactivity control capability and high reactor core conversion capability so as to obtain a longer refueling period, and the safety and the economy of neutrons are obviously improved.

Description

technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a thorium-based fuel assembly and a small pressurized water reactor. Background technique [0002] Small pressurized water reactors have outstanding advantages such as system simplification and flexible operation, and are widely used, such as: power supply in remote areas and offshore, low-temperature heating, seawater desalination, and cogeneration of water, electricity, and heat for other purposes. In order to improve economical efficiency and market competitiveness, the refueling cycle needs to reach 5-10 years, and the integrated refueling method is adopted, which is quite different from the 12-18 month batch refueling adopted by nuclear power plants. [0003] At present, the core design of small pressurized water reactors mainly improves the reactivity control capability of the core by increasing the amount of burnable poison and the number of control rods arranged,...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/60G21C5/16
CPCG21C3/60G21C5/16Y02E30/30
Inventor 夏榜样卢川
Owner NUCLEAR POWER INSTITUTE OF CHINA
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