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Coolant staggered-flowing-type fuel assembly and supercritical water-cooled reactor

A fuel assembly and coolant technology, applied in the field of nuclear reactors, can solve problems such as the complexity of fuel assembly structure and core structure, and achieve simplified fuel assembly schemes and core structure schemes, simplified fuel assembly schemes, and thermal safety margins Enhanced effect

Active Publication Date: 2020-02-21
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] The object of the present invention is to provide a fuel assembly with interleaved flow of coolant and a supercritical water-cooled reactor, which uses a simple structure to realize the combination of the control rod arrangement area, the low-temperature coolant channel, and the neutron moderation area, as well as the concealment of the coolant at the assembly scale. Multi-process flow, instead of complex multi-process implementation of coolant at the core scale, thus effectively solving the existing fuel assembly structure and Complexity of core structure, while ensuring core coolant flow rate, enhanced heat transfer capacity, to obtain higher design performance

Method used

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  • Coolant staggered-flowing-type fuel assembly and supercritical water-cooled reactor
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  • Coolant staggered-flowing-type fuel assembly and supercritical water-cooled reactor

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Embodiment 1

[0030] Such as figure 1 , figure 2 As shown, a coolant staggered flow fuel assembly, the fuel assembly is an inner box 1, a heat insulation enclosure 2 and an outer box 3 from the inside to the outside along the radial direction. The inner box 1 contains an area In zone I, the area between the inner box 1 and the heat-insulating enclosure 2 is zone II, and the area between the heat-insulating enclosure 2 and the outer box 3 is zone III. There is no fuel rod in the I zone, and there is 1 guide pipe 4, low-enrichment fuel rods 5 are arranged in zone II, and the enrichment degree of the low-enrichment fuel rods 5 is 3.7%, and high-enrichment fuel rods 6 are arranged in zone III. The degree of enrichment of the fuel rod 6 is 5.7%; both ends of the fuel assembly are provided with a lower head 7 and an upper head 8, respectively, the lower head 7 is provided with a lower head diversion hole 9, so The upper head 8 is provided with an upper head diversion hole 10, the lower head diver...

Embodiment 2

[0032] Example 2 (core solution):

[0033] Such as Figure 4 As shown, a supercritical water-cooled reactor composed of fuel assemblies with interleaved coolant flows described in Example 1, and the core adopts 177 cartridges such as image 3 The coolant staggered flow type square fuel assembly 11 is shown, the center distance between adjacent fuel assemblies is 171mm, the water gap between the fuel assemblies is 1.4mm, the height of the reactor core active area is 3600.0mm, and the diameter of the circumscribed circle is 2704.0mm , The volume average power density is 64.4MW / m 3 , The average linear power density is 11.8kW / m. After entering the reactor from the cold end of the pressure vessel, the cryogenic coolant enters the lower chamber of the pressure vessel down the annular cavity of the pressure vessel, enters the module I area from the bottom of the fuel assembly 11, and exits the reactor from the module III area. The detailed design parameters of the reactor core are sho...

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Abstract

The invention discloses a coolant staggered-flowing-type fuel assembly and a supercritical water-cooled reactor. According to the coolant staggered-flowing-type fuel assembly, a fuel assembly is sequentially provided with an inner box, a heat insulation shroud and an outer box from inside to outside in the radial direction; an area contained in the inner box is area I; an area between the inner box and the heat insulation shroud is area II; an area between the heat insulation shroud and the outer box is area III; a guide pipe is arranged in the area I; a low-enrichment-degree fuel rod is arranged in the area II, a high-enrichment-degree fuel rod is arranged in the area III, a lower end socket and an upper end socket are arranged at the two ends of the fuel assembly respectively, a lower end socket flow guide hole is formed in the lower end socket, an upper end socket flow guide hole is formed in the upper end socket, and a coolant flows in the area I, the area II and the area III in astaggered mode. The invention can solve the problem of complication of a fuel assembly and a reactor core structure due to the adoption of a water slowing-down rod and coolant multi-flow design technology in the prior art, and has the advantages of improving the flow rate of a reactor core coolant, enhancing heat transfer and reducing the temperature of a fuel cladding.

Description

Technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a coolant staggered flow fuel assembly and a supercritical water-cooled reactor. Background technique [0002] Supercritical water-cooled reactor (SCWR) is one of the six most promising advanced nuclear energy systems selected by the IV Nuclear Energy International Forum (GIF). In order to obtain higher thermal efficiency for the supercritical water-cooled reactor (SCWR) nuclear power unit, the average outlet temperature of the core coolant needs to be above 500°C, which leads to a higher temperature on the outer surface of the fuel cladding, giving it safety during long-term operation Brings great challenges. In order to solve this problem, under the condition that the total flow rate of the reactor coolant remains unchanged, the core needs to be divided into multiple flow zones along the radial direction, that is, the "multi-flow" flow scheme, to increase the flow rate of ...

Claims

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Application Information

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IPC IPC(8): G21C15/243G21C15/02
CPCG21C15/02G21C15/243Y02E30/30
Inventor 夏榜样姚磊卢迪王连杰李庆李翔肖鹏甯忠豪李司南
Owner NUCLEAR POWER INSTITUTE OF CHINA
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