CN113593729A - Fast neutron reactor high-burnup metal fuel element using graphite foam as heat-conducting medium - Google Patents
Fast neutron reactor high-burnup metal fuel element using graphite foam as heat-conducting medium Download PDFInfo
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- CN113593729A CN113593729A CN202110851689.9A CN202110851689A CN113593729A CN 113593729 A CN113593729 A CN 113593729A CN 202110851689 A CN202110851689 A CN 202110851689A CN 113593729 A CN113593729 A CN 113593729A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/044—Fuel elements with porous or capillary structure
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/17—Means for storage or immobilisation of gases in fuel elements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/18—Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention provides a high-burnup metal fuel element of a fast neutron reactor using graphite foam as a heat-conducting medium, and relates to the technical field of nuclear engineering. The method comprises the following steps: the fuel core and the cladding arranged outside the side wall of the core are filled with porous heat-conducting media. According to the invention, the high-porosity porous heat-conducting medium with good heat conductivity is selected in the fuel-cladding gap to replace liquid sodium in the traditional fuel as the heat-conducting medium, so that a plurality of 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
The invention relates to the technical field of nuclear engineering, in particular to a high-burnup metal fuel element of a fast neutron reactor using graphite foam as a heat-conducting medium.
Background
The fast neutron reactor (fast reactor for short) is the key to greatly improve the utilization rate of uranium resources and realize closed circulation of fuel. The uranium zirconium/uranium plutonium zirconium (U-Zr/U-Pu-Zr) alloy has good heat transfer performance and good compatibility with cladding materials, and is considered to be one of the main candidate fuels of advanced reactors such as sodium-cooled fast reactors.
According to the present data, the uranium zirconium/uranium plutonium zirconium alloy exhibits anisotropic rapid swelling after irradiation in the reactor and starts with significant fission gas release starting from burn-up to only around 1-2% Ferma (FIMA). Initially, factors such as fuel swelling, fission gas release, Fuel Cladding Mechanical Interaction (FCMI) greatly limit the burn-up life of uranium zirconium/uranium plutonium zirconium alloys. By reducing the volume of fuel in the cladding and increasing the volume of an air cavity for containing fission gas, the problems of internal pressure increase caused by the release of the fuel fission gas, fuel-cladding mechanical interaction (FCMI) caused by swelling and the like are greatly relieved, and the optimized uranium zirconium alloy can reach the maximum fuel consumption of 10-20%. At present, fuel-cladding chemical interaction (FCCI) becomes a key factor limiting the attainment of higher burnup of uranium zirconium/uranium plutonium zirconium alloys at higher burnup.
In order to accommodate the swelling of the fuel, a large gap is reserved between the fuel and the cladding in the conventional uranium zirconium metal fuel. In order to reduce the temperature of the fuel, the fuel-cladding gap is filled with liquid sodium as a heat transfer medium. The main advantages of liquid sodium are a small cross-section for reaction with neutrons and at the same time a high thermal conductivity, which is about 65W/(m · K) at 550 ℃. However, the addition of liquid sodium on the one hand entails considerable inconveniences for the post-treatment of the fuel, and on the other hand recent studies have shown that liquid sodium may greatly accelerate the diffusion of the fission products of the lanthanides into the cladding. The lanthanide fission products (mainly neodymium and cerium) can obviously reduce the effective wall thickness and the local mechanical property of the cladding after being rapidly diffused to the cladding, and are the main causes for the breakage of the cladding under higher burnup. Therefore, in order to achieve higher fuel consumption, a new uranium zirconium alloy fuel without a liquid sodium heat transfer medium needs to be designed, so as to avoid the adverse effect of liquid sodium in a fuel element on fuel-cladding chemical interaction and aftertreatment.
Disclosure of Invention
The invention aims to provide a high-burnup metal fuel element of a fast neutron reactor using graphite foam as a heat-conducting medium, aiming at overcoming the defects in the prior art, the element selects a high-porosity porous heat-conducting medium with good heat conductivity in a fuel-cladding gap to replace liquid sodium in the traditional fuel as the heat-conducting medium, avoids the problems caused by the liquid sodium in the preparation of the fuel and the post-treatment of spent fuel, and is expected to remarkably prolong the burnup life of the uranium zirconium alloy.
The invention aims to provide a high-burnup metal fuel element of a fast neutron reactor using graphite foam as a heat-conducting medium, which comprises the following components:
the fuel core and the cladding arranged outside the side wall of the core are filled with porous heat-conducting media.
Preferably, the porosity of the porous heat-conducting medium is 65-75%, and the pore size is 50-100 μm.
Preferably, the thermal conductivity of the porous heat-conducting medium is equal to or more than 100W/(m.K).
Preferably, the porous heat-conducting medium is graphite foam.
Preferably, the gap between the core and the cladding has a dimension of 1.2 ± 0.1 mm.
Preferably, a gap between the core and the cladding is further filled with helium.
Preferably, the center of the core body is further provided with a through hole, and helium is filled in the through hole.
Preferably, the core body is made of uranium zirconium alloy.
Preferably, the cladding wall thickness is 0.6 ± 0.1 mm.
More preferably, the material of the cladding is ferrite-martensite steel.
Compared with the prior art, the invention has the beneficial effects that:
according to the invention, the high-porosity porous heat-conducting medium with good heat conductivity is selected in the fuel-cladding gap to replace liquid sodium in the traditional fuel as the heat-conducting medium, so that a plurality of 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.
The high-burnup metal fuel element of the fast neutron reactor with the graphite foam as the heat-conducting medium provided by the invention selects the porous heat-conducting medium with the porosity of 65-75% in the fuel-cladding gap, and particularly adopts the graphite foam as the heat-conducting medium, so that the heat conductivity can reach 100-180W/(m.K), the compression strength is about 10MPa, and the structure and the performance are stable at 700 ℃.
The fuel element provided by the invention adopts graphite foam as a heat-conducting medium, and the fuel of the fuel element starts to be in direct contact with the cladding after about 1% of Feima is combusted, and the fission gas is released. During subsequent service, swelling of the fuel is mainly manifested as longitudinal elongation. At burnup below 1%, according to empirical data, the internal fuel element pressure will be less than 5MPa, and therefore will not significantly affect the structure of the heat transfer medium graphite foam. At higher burnup, the fuel will gradually occupy the original void position in the graphite foam after swelling and begin to transfer heat in a heat conduction manner in direct contact with the cladding, and the importance of the porous medium graphite foam to heat transfer will gradually decrease.
The element provided by the invention greatly relieves the chemical interaction of the fuel cladding, obviously prolongs the burnup life of the fast reactor fuel and improves the utilization efficiency of uranium; the overall economy and safety of the fast reactor are improved through the novel fuel design; liquid sodium heat-conducting medium in the traditional uranium zirconium/uranium plutonium zirconium alloy fuel is removed, and the post-treatment of the fuel is facilitated.
Drawings
Fig. 1 is a schematic structural diagram of a fast neutron reactor high-burnup metal fuel element using graphite foam as a heat transfer medium provided in example 1.
Fig. 2 is a schematic cross-sectional structural view of a fast neutron reactor high-burnup metal fuel element using graphite foam as a heat transfer medium provided in example 1.
Fig. 3 is a schematic structural diagram of a fast neutron reactor high-burnup metal fuel element using graphite foam as a heat transfer medium provided in examples 2 and 3.
Fig. 4 is a neutron spectrum comparison chart of the fast neutron reactor high-burnup metal fuel element using the graphite foam as the heat conducting medium of example 1 and comparative example 1.
Detailed Description
In order to make the technical solutions of the present invention better understood and enable those skilled in the art to practice the present invention, the following embodiments are further described, but the present invention is not limited to the following embodiments.
The following embodiments illustrate the elements provided by the present invention by taking the uranium zirconium alloy fuel design in a sodium-cooled fast reactor as an example.
Example 1
A fast neutron reactor high-burnup metal fuel element taking graphite foam as a heat-conducting medium is shown in figures 1-2 and comprises:
the fuel core 1 and the cladding 3 arranged outside the side wall of the core 1 are filled with the porous heat-conducting medium 2 between the core 1 and the cladding 3.
The fuel core body 1 is a cylindrical fuel rod with the diameter of 4.8mm and is made of uranium zirconium alloy;
the cladding 3 material is a ferritic-martensitic steel,
the wall thickness of the envelope 3 is 0.6mm,
the inner diameter of the cladding 3 is 6.0 mm;
the porous heat-conducting medium 2 is graphite foam with the porosity of 70 percent (the equivalent density is 0.68 g/cm)3) The average pore size was 70 μm, the thermal conductivity was 150W/(m.K), and the interior thereof was filled with helium gas.
The fuel core provided by the embodiment needs to reserve a part of space above or below the fuel core as an air cavity for containing fission gas, and the structure of the fuel core is the same as that of a traditional uranium zirconium metal fuel element. Thus, the air cavities are not shown in FIGS. 1-2.
Example 2
A fast neutron reactor high-burnup metal fuel element using graphite foam as a heat-conducting medium, as shown in fig. 3, comprising:
the fuel core 1 and the cladding 3 arranged outside the side wall of the core 1 are filled with the porous heat-conducting medium 2 between the core 1 and the cladding 3.
The core body is still made of uranium zirconium alloy;
in order to reduce the central temperature of the fuel, the center of the fuel core 1 is also provided with a through hole 11, the radius of the through hole 11 is 1/3 of the outer radius of the core, and helium is filled in the through hole;
the cladding 3 material is a ferritic-martensitic steel,
the wall thickness of the envelope 3 is 0.6mm,
the inner diameter of the cladding 3 is 6.0 mm;
the porous heat-conducting medium 2 is graphite foam with the porosity of 70 percent (the equivalent density is 0.68 g/cm)3) The average pore size was 70 μm, the thermal conductivity was 150W/(m.K), and the interior thereof was filled with helium gas.
The fuel core provided by the embodiment needs to reserve a part of space above or below the fuel core as an air cavity for containing fission gas, and the structure of the fuel core is the same as that of a traditional uranium zirconium metal fuel element.
Example 3
A fast neutron reactor high-burnup metal fuel element using graphite foam as a heat-conducting medium, as shown in fig. 3, comprising:
the fuel core 1 and the cladding 3 arranged outside the side wall of the core 1 are filled with the porous heat-conducting medium 2 between the core 1 and the cladding 3.
The core body is still made of uranium zirconium alloy;
in order to reduce the central temperature of the fuel, the center of the fuel core 1 is also provided with a through hole 11, the radius of the through hole 11 is 1/2 of the outer radius of the core, and helium is filled in the through hole;
the cladding 3 material is a ferritic-martensitic steel,
the wall thickness of the envelope 3 is 0.6mm,
the inner diameter of the cladding 3 is 6.0 mm;
the porous heat-conducting medium 2 is graphite foam with the porosity of 70 percent (the equivalent density is 0.68 g/cm)3) The average pore size was 70 μm, the thermal conductivity was 150W/(m.K), and the interior thereof was filled with helium gas.
The fuel core provided by the embodiment needs to reserve a part of space above or below the fuel core as an air cavity for containing fission gas, and the structure of the fuel core is the same as that of a traditional uranium zirconium metal fuel element.
Comparative example 1
The same as in example 1 except that liquid sodium was substituted for the porous heat transfer medium.
In order to verify the potential influence of porous graphite in the high-burnup metal fuel element of the fast neutron reactor using the graphite foam as the heat-conducting medium, provided by the invention, on the neutron energy spectrum, comparative analysis of fast neutron flux was performed on the fuel elements provided in example 1 and comparative example 1, and see fig. 4
Fig. 4 is a neutron energy spectrum of a fast neutron reactor high-burnup metal fuel element using graphite foam as a heat conducting medium provided in example 1 and comparative example 1.
As can be seen from fig. 4, when the neutron spectrum in the fuel rod is compared between the case of using sodium and the case of using the porous graphite foam as the heat transfer medium, it can be seen that the moderating effect of the porous graphite on the neutron spectrum is very small. Therefore, from a reactor physical point of view, it is feasible to use porous graphite foam instead of liquid sodium.
From the perspective of fuel preparation and spent fuel aftertreatment, the fuel design well avoids a plurality of problems caused by liquid sodium, can break through the fuel consumption limit (exceeding 20% phenanthrma) of the existing uranium zirconium/uranium plutonium zirconium alloy fuel, and can better meet the design requirements of various fast reactors.
In conclusion, according to the high-burnup metal fuel element of the fast neutron reactor using graphite foam as the heat-conducting medium, the high-porosity porous heat-conducting medium with good heat conductivity is selected in the fuel-cladding gap to replace liquid sodium in the traditional fuel as the heat-conducting medium, so that the problems caused by the liquid sodium in the fuel preparation and spent fuel aftertreatment are avoided, and the burnup life of the uranium zirconium alloy is expected to be remarkably prolonged.
According to the fuel element provided by the invention, the porous heat-conducting medium with the porosity of 65-75% is selected in the fuel-cladding gap, specifically, graphite foam is used as the heat-conducting medium, the heat conductivity can reach 100-180W/(m.K), the compression strength can reach about 10MPa, and the structure and the performance are stable at 700 ℃.
The fuel element provided by the invention adopts graphite foam as a heat-conducting medium, and the fuel of the fuel element starts to be in direct contact with the cladding after about 1% of Feima is combusted, and the fission gas is released. During subsequent service, swelling of the fuel is mainly manifested as longitudinal elongation. At burnup below 1%, according to empirical data, the internal fuel element pressure will be less than 5MPa, and therefore will not significantly affect the structure of the heat transfer medium graphite foam. At higher burnup, the fuel will gradually occupy the original void position in the graphite foam after swelling and begin to transfer heat in a heat conduction manner in direct contact with the cladding, and the importance of the porous medium graphite foam to heat transfer will gradually decrease.
In order to avoid the liquid sodium from accelerating the diffusion of lanthanide fission products to the cladding, porous medium graphite foam with good heat transfer performance is used for replacing the liquid sodium as a heat transfer medium between the fuel and the cladding; reserving sufficient porosity in the porous media to accommodate swelling of the uranium zirconium/uranium plutonium zirconium alloy, significantly reducing FCMI; the traditional manufacturing process of the uranium zirconium/uranium plutonium zirconium alloy fuel rod does not need to be changed, and only the porous heat-conducting medium needs to be placed between the fuel and the cladding, so that the production process of the fuel element is greatly simplified, and the manufacturing cost of the fuel is reduced.
While preferred embodiments of the present invention have been described, additional variations and modifications in those embodiments may occur to those skilled in the art once they learn of the basic inventive concepts. Therefore, it is intended that the appended claims be interpreted as including preferred embodiments and all such alterations and modifications as fall within the scope of the invention.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (10)
1. A fast neutron reactor high-burnup metal fuel element taking graphite foam as a heat-conducting medium is characterized by comprising:
the fuel core and the cladding arranged outside the side wall of the core are filled with porous heat-conducting media.
2. The fast neutron reactor high-burnup metal fuel element taking graphite foam as a heat-conducting medium according to claim 1, wherein the porosity of the porous heat-conducting medium is 65-75%, and the pore size is 50-100 μm.
3. The fast neutron reactor high-burnup metal fuel element with graphite foam as the heat conducting medium according to claim 1, wherein the heat conductivity of the porous heat conducting medium is equal to or more than 100W/(m-K).
4. The fast neutron reactor high-burnup metal fuel element with graphite foam as the heat conducting medium according to claim 1, wherein the porous heat conducting medium is graphite foam.
5. The fast neutron reactor high-burnup metal fuel element with graphite foam as the heat conducting medium according to claim 1, wherein the gap size between the core and the cladding is 1.2 ± 0.1 mm.
6. The fast neutron reactor high-burnup metal fuel element with graphite foam as the heat conducting medium according to claim 1, characterized in that a gap between the core and the cladding is further filled with helium.
7. The fast neutron reactor high-burnup metal fuel element taking graphite foam as a heat-conducting medium according to claim 1, wherein a through hole is further formed in the center of the core body, and helium is filled in the through hole.
8. The fast neutron reactor high-burnup metal fuel element taking graphite foam as a heat-conducting medium according to claim 1, wherein the core body is made of uranium zirconium alloy.
9. The fast neutron reactor high-burnup metal fuel element with graphite foam as the heat conducting medium according to claim 1, wherein the cladding wall thickness is 0.6 ± 0.1 mm.
10. The fast neutron reactor high-burnup metal fuel element with graphite foam as the heat conducting medium according to claim 7, wherein the material of the cladding is ferrite-martensite steel.
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| CN202110851689.9A CN113593729A (en) | 2021-07-27 | 2021-07-27 | Fast neutron reactor high-burnup metal fuel element using graphite foam as heat-conducting medium |
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| CN202110851689.9A CN113593729A (en) | 2021-07-27 | 2021-07-27 | Fast neutron reactor high-burnup metal fuel element using graphite foam as heat-conducting medium |
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