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Fast neutron reactor high-burnup metal fuel element with graphite foam as heat-conducting medium

A heat-conducting medium and graphite foam technology, which is applied in the field of nuclear engineering, can solve the problems of accelerating the diffusion of lanthanide fission products and the inconvenience of fuel post-processing, and achieve the effects of improving the overall economy, stable structure and performance, and improving the fuel consumption life

Pending Publication Date: 2021-11-02
ZHEJIANG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, on the one hand, the addition of liquid sodium brings a lot of inconvenience to the reprocessing of the fuel; on the other hand, recent studies have shown that liquid sodium may greatly accelerate the diffusion of lanthanide fission products into the cladding

Method used

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  • Fast neutron reactor high-burnup metal fuel element with graphite foam as heat-conducting medium
  • Fast neutron reactor high-burnup metal fuel element with graphite foam as heat-conducting medium
  • Fast neutron reactor high-burnup metal fuel element with graphite foam as heat-conducting medium

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Embodiment 1

[0029] A fast neutron reactor high burnup metal fuel element with graphite foam as heat conduction medium, see Figure 1~2 shown, including:

[0030] The fuel core 1 and the cladding 3 provided on the side wall of the core 1 are filled with a porous heat-conducting medium 2 between the core 1 and the cladding 3 .

[0031] The fuel core 1 is a cylindrical fuel rod with a diameter of 4.8 mm and made of uranium-zirconium alloy;

[0032] The cladding 3 is made of ferritic-martensitic steel,

[0033] The wall thickness of the cladding 3 is 0.6mm,

[0034] The inner diameter of the cladding 3 is 6.0mm;

[0035] The porous heat-conducting medium 2 is graphite foam with a porosity of 70% (equivalent density 0.68g / cm 3 ), the average pore size is 70 μm, the thermal conductivity is 150 W / (m K), and the interior is filled with helium.

[0036] In the fuel core body provided in this embodiment, a part of space needs to be reserved above or below the fuel core body as an air cavity fo...

Embodiment 2

[0038] A fast neutron reactor high burnup metal fuel element with graphite foam as heat conduction medium, see image 3 shown, including:

[0039] The fuel core 1 and the cladding 3 provided on the side wall of the core 1 are filled with a porous heat-conducting medium 2 between the core 1 and the cladding 3 .

[0040] The core material is still uranium-zirconium alloy;

[0041] In order to reduce the temperature of the fuel core, a through hole 11 is opened in the center of the fuel core body 1. The radius of the through hole 11 is 1 / 3 of the outer radius of the core, and the through hole is filled with helium;

[0042] The cladding 3 is made of ferritic-martensitic steel,

[0043] The wall thickness of the cladding 3 is 0.6mm,

[0044] The inner diameter of the cladding 3 is 6.0mm;

[0045] The porous heat-conducting medium 2 is graphite foam with a porosity of 70% (equivalent density 0.68g / cm 3 ), the average pore size is 70 μm, the thermal conductivity is 150 W / (m K),...

Embodiment 3

[0048] A fast neutron reactor high burnup metal fuel element with graphite foam as heat conduction medium, see image 3 shown, including:

[0049] The fuel core 1 and the cladding 3 provided on the side wall of the core 1 are filled with a porous heat-conducting medium 2 between the core 1 and the cladding 3 .

[0050] The core material is still uranium-zirconium alloy;

[0051] In order to reduce the temperature of the fuel core, a through hole 11 is opened in the center of the fuel core body 1. The radius of the through hole 11 is 1 / 2 of the outer radius of the core, and the through hole is filled with helium;

[0052] The cladding 3 is made of ferritic-martensitic steel,

[0053] The wall thickness of the cladding 3 is 0.6mm,

[0054] The inner diameter of the cladding 3 is 6.0mm;

[0055] The porous heat-conducting medium 2 is graphite foam with a porosity of 70% (equivalent density 0.68g / cm 3), the average pore size is 70 μm, the thermal conductivity is 150 W / (m K), ...

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Abstract

The invention provides a fast neutron reactor high-burnup metal fuel element with graphite foam as a heat-conducting medium, and relates to the technical field of nuclear engineering. The metal fuel element comprises a fuel core body and a cladding arranged outside the side wall of the core body, wherein a porous heat-conducting medium is filled between the core body and the cladding. The high-porosity porous heat-conducting medium with good heat conductivity is selected in the gap between the fuel and the cladding to replace liquid sodium in traditional fuel to serve as the heat-conducting medium, many problems caused by the liquid sodium in fuel preparation and spent fuel aftertreatment are avoided, and the fuel consumption life of the uranium-zirconium alloy is expected to be remarkably prolonged.

Description

technical field [0001] The invention relates to the technical field of nuclear engineering, in particular to a metal fuel element with high burnup consumption of a fast neutron reactor using graphite foam as a heat conducting medium. Background technique [0002] Fast neutron reactors (referred to as fast reactors) are the key to greatly improving the utilization of uranium resources and realizing a closed fuel cycle. Uranium-zirconium / uranium-plutonium-zirconium (U-Zr / U-Pu-Zr) alloys have good heat transfer properties and good compatibility with cladding materials, so they are considered to be the main candidate fuels for advanced reactors such as sodium-cooled fast reactors one. [0003] According to the available data, uranium-zirconium / uranium-plutonium-zirconium alloys exhibit anisotropic rapid swelling after irradiation in the reactor, and significant fission gas release begins when the burnup reaches only about 1-2% FIMA. Initially, factors such as fuel swelling, fi...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/04G21C3/17G21C3/18
CPCG21C3/044G21C3/17G21C3/18Y02E30/30
Inventor 刘翔恽迪张少泓
Owner ZHEJIANG UNIV
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