CN102789820B - Nuclear fuel rod - Google Patents
Nuclear fuel rod Download PDFInfo
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- CN102789820B CN102789820B CN201210293447.3A CN201210293447A CN102789820B CN 102789820 B CN102789820 B CN 102789820B CN 201210293447 A CN201210293447 A CN 201210293447A CN 102789820 B CN102789820 B CN 102789820B
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- fuel rod
- fuel
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- liner
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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
Abstract
The invention relates to a nuclear fuel rod which comprises a fuel pellet and a jacket of the fuel rod arranged around the fuel pellet; and the nuclear fuel rod further comprises a supporting lining supported between the fuel pellet and the jacket of the fuel rod. Due to the supporting lining arranged between the fuel pellet and the jacket of the fuel rod, the internal pressure of the nuclear fuel rod can be reduced, more fission gases can be contained, the heat dissipation of the fuel pellet can be strengthened, the PCI (pellet-cladding mechanical interaction) phenomenon caused by thermal expansion can be released, and the strain energy acting on the jacket of the fuel rod can be reduced, so that the risk of damage of the PCI can be reduced, and the operation safety of a reactor of a nuclear station can be greatly improved.
Description
Technical field
The present invention relates to nuclear power plant reactor, more particularly, relate to a kind of nuclear fuel rod that can be used in PWR of Nuclear Power Station.
Background technology
In the operation of nuclear power plant reactor, the breakage of nuclear fuel rod makes the radioactive fission product in nuclear fuel rod be discharged in the coolant system of reactor, thus jeopardizes the normal operation of nuclear power station.PCI is one of Latent destruction factor of nuclear fuel rod.PCI or PCMI is exactly the abbreviation of English Pellet-Cladding Mechanical Interaction, refers to fuel pellet and the mechanical interaction of involucrum in nuclear power station operational process.
Usually, nuclear fuel rod comprises fuel pellet and is arranged on the fuel rod clad etc. of fuel pellet periphery.There is certain primary clearance between fuel rod clad and fuel pellet, be full of in gap helium (He gas) as heat eliminating medium and provide interior pressure with balance fuel rod involucrum suffered by external pressure.
Along with the intensification running burnup, the solid fission product in fuel pellet and gas fission product are taken in a large number in fuel pellet, make fuel pellet generation void swelling, and fuel pellet diameter increases.Fuel pellet is under the effect of high temperature difference simultaneously, and ftracture, cause the reorientation of fuel pellet, part fragment is between fuel pellet and fuel rod clad.
On the other hand, fuel rod clad is normally made by zircaloy, in the irradiation and reactor of neutron cooling medium hydraulic pressure effect under, radial produce creep and shrink, the internal diameter of fuel rod clad is reduced.
And fuel pellet and fuel rod clad are different materials, and the thermal expansion of fuel pellet is greater than fuel rod clad.In heap in operational process, the temperature of fuel pellet is far away higher than the medial temperature of involucrum, and the thermal expansion amount of such fuel pellet is much higher than the thermal expansion amount of fuel rod clad.
Therefore, under the synergy of the inside creep of void swelling, thermal expansion and fuel rod clad, along with the intensification of fuel-assembly burn-up, the diametric clearance of fuel rod clad and fuel pellet reduces, until closed, PCI to occur.
Owing to there is the risk that PCI destroys, in the operation of nuclear power station, nuclear power station just can not exceed operating standard fast lifting reactor capability, can not low power run for a long time.In the process of fast lifting reactor capability, fuel pellet temperature raises rapidly and rapid expanding, the thermal expansion of fuel rod clad and outside creep is made to have little time to offset the thermal expansion of fuel pellet, thus the stress making involucrum bear exceedes the yield strength of involucrum, fuel rod clad is caused to destroy because of PCI.
Reducing in the process of reactor capability fast, due to the motion of control rod, the axial power distribution of reactor becomes unusual, makes the partial power of nuclear fuel rod be much higher than average power, produce the phenomenon identical with fast lifting power, cause fuel rod clad to destroy because of PCI.
Nuclear power plant reactor runs for a long time under low-power, pressure in nuclear fuel rod is well below the operating pressure of reactor-loop, this exacerbates fuel rod clad due to the inside creep of the effect of external pressure, the gap of involucrum and pellet is reduced, cause fuel pellet to contact in advance with fuel rod clad, once reactor capability changes, add the stressed load of involucrum, increase the risk that PCI destroys, cause fuel rod clad destroy because of PCI thus nuclear leakage occurs.
Existing nuclear fuel rod cannot adapt to the risk that above-mentioned PCI destroys, and runs bring uncertainty to nuclear plant safety.
Summary of the invention
The technical problem to be solved in the present invention is, provides a kind of nuclear fuel rod effectively can alleviated PCI and destroy.
The technical solution adopted for the present invention to solve the technical problems is: construct a kind of nuclear fuel rod, comprises fuel pellet and is arranged on the fuel rod clad of described fuel pellet periphery; Described nuclear fuel rod also comprises the support liner be supported between described fuel pellet and fuel rod clad.
In nuclear fuel rod of the present invention, described support liner is flexible liner.
In nuclear fuel rod of the present invention, described support liner is arranged in the segment space between described fuel pellet and fuel rod clad, and is filled with helium in space between described fuel pellet and fuel rod clad.
In nuclear fuel rod of the present invention, described support liner is made up of one or more metal material, is arranged on the periphery of described fuel pellet.
In nuclear fuel rod of the present invention, described metal material is pure zirconium, zircaloy or inconel.
In nuclear fuel rod of the present invention, described support liner directly contacts with fuel rod clad with described fuel pellet simultaneously; The cross sectional shape of described support liner is wavy, zigzag or square-wave-shaped.
In nuclear fuel rod of the present invention, described support liner is made up of polylith metal material, and the cross sectional shape of each block metal material is arc.
In nuclear fuel rod of the present invention, described support liner also comprises the inner liner support plate directly contacting connection with described fuel pellet;
One end of described metal material directly contacts connection with described fuel rod clad, and the other end is fixedly connected with described inner liner support plate.
In nuclear fuel rod of the present invention, described nuclear fuel rod also comprises upper end, lower end, the support column be arranged on described lower end, the holddown spring be arranged on described upper end;
Described fuel pellet is arranged between described holddown spring and support column, and described fuel rod clad is arranged between described upper end and lower end.
In nuclear fuel rod of the present invention, described support liner is ring-type, is arranged on inside described fuel rod clad, for monoblock type or multistage split type.
Implement the present invention and there is following beneficial effect: by arranging support liner between fuel pellet and fuel rod clad, the interior pressure of nuclear fuel rod can be reduced, hold more fission gas, the heat radiation to fuel pellet can be strengthened, alleviate PCI phenomenon, all right reducing effect, in the strain energy of fuel rod clad, reduces risk PCI occurring and destroys, substantially increases the security that nuclear power plant reactor runs.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is the structural representation of a nuclear fuel rod of the present invention embodiment;
Fig. 2 is the schematic cross-section of a nuclear fuel rod of the present invention embodiment;
Fig. 3 is that nuclear fuel rod of the present invention adopts waveform to support the schematic diagram of liner;
Fig. 4 is the schematic diagram that nuclear fuel rod of the present invention adopts curved support liner.
Embodiment
As shown in Figure 1, 2, be an embodiment of nuclear fuel rod of the present invention, can be used in the reactor of nuclear power station.This nuclear fuel rod comprises fuel pellet 11, fuel rod clad 12, supports liner 13 etc.This nuclear fuel rod can also comprise the installing mechanisms such as upper end 14, lower end 15, the support column 16 be arranged on lower end 15, the holddown spring 17 be arranged on upper end 14, for fixedly mounting fuel pellet 11 and fuel rod clad 12; Certainly, installing mechanism also can adopt other forms of mounting structure.
As shown in the figure, this fuel pellet 11 is arranged between holddown spring 17 and support column 16, and fuel rod clad 12 is arranged between upper end 14 and lower end 15, gap is formed between fuel rod clad 12 and fuel chip, supporting liner 13 is arranged in gap, and contact with fuel rod clad 12 with fuel pellet 11, play a supporting role.Solid material can be selected to make owing to supporting liner 13, can be arranged in the segment space between fuel pellet 11 and fuel rod clad 12, because its thermal conductivity is far above the helium in fuel rod, the heat radiation to fuel pellet 11 can be strengthened, suppress fuel pellet 11 overexpansion.In addition, helium can also be filled with in the space further between fuel pellet 11 and fuel rod clad 12.
This support liner 13 can select flexible liner, and the elastic potential energy that the strain energy directly acting on fuel rod clad 12 inwall can be converted to flexible liner is stored up, and implements buffering, make it not easily wreck to fuel rod clad 12.
This support liner 13 can be made up of the solid material that thermal neutron absorption cross section is very little, selects this type of material to be neutron economy in order to ensure in reactor.In the present embodiment, this support liner 13 selects pure zirconium to be flexible liner material, and the thermal neutron absorption cross section of pure zirconium is very little, is about 0.185b(1b=1 × 10
-28m
2), neutron economy enough in anti-heap can be guaranteed.In addition, pure zirconium phase transition temperature 862 DEG C.When nuclear power station runs under worst two class transient states, the linear power density of fuel is no more than 400KW/cm, and fuel pellet 11 surface temperature is correspondingly about 450 DEG C, far below the phase transition temperature of pure zirconium.Therefore under the most severe two class transient states, the support liner 13 be made up of pure zirconium still has suitable elasticity and intensity, now, supporting liner 13 still can provide supporting to prevent it from caving in fuel rod clad 12, and the mechanical energy of pellet expansion can be stored by elastic deformation, buffering is implemented to fuel rod clad 12, has greatly cushioned the effect energy of pellet to involucrum.
Certainly, support liner 13 and other material can also be selected to make, the material that such as zircaloy, inconel etc. are conventional in nuclear power field.
Supporting liner 13 is solid, and its thermal conductivity is much larger than He gas.Such as, pure zirconium thermal conductivity is 0.227W/cmK, be about He(0.00152W/cmK) 150 times, can the surface radiating of efficient hardening fuel pellet 11, reduce fuel pellet 11 surface temperature and suppress its overall overexpansion, significantly can reduce fuel pellet 11 because of thermal expansion to the stress supporting liner 13 and fuel rod clad 12 applying.Further, the length of this support liner 13 need exceed the length of the active section of fuel pellet 11, thus can better be derived by heat.
In addition, too much He gas need not be filled with to maintain thermal conductivity and interior pressure (for external pressure suffered by balance fuel rod involucrum 12 in nuclear fuel rod, this external pressure is from light water coolant), just can hold more fission gas in such nuclear fuel rod, make the burnup that nuclear fuel rod can reach higher.
This support liner 13 can do circlewise, all contact with fuel rod clad 12 with fuel pellet 11, therefore the external pressure suffered by fuel rod clad 12 can be passed to fuel pellet 11, hard fuel pellet 11 can become the support of fuel rod clad 12, prevent fuel rod clad 12 because at high temperature past fuel pellet 11 direction caves in by external force generation creep, cause contacting of fuel rod clad 12 and fuel pellet 11; Support the barrier of liner 13 as fuel rod clad 12, intercept the pollution of fission product.
In addition, support the bridle that liner 13 becomes fuel pellet 11, the probability that fuel pellet 11 is reorientated after void swelling or generation fragmentation declines.Fuel pellet 11 directly contacts with support liner 13, even if because strain energy is excessive or Contamination of Fission Product initiation stress corrosion causes support liner 13 that rupture failure occurs, this damage effect also can not be delivered to fuel rod clad 12, and supporting liner 13 is expendable barrier concerning fuel rod clad 12.
As shown in Figure 3, this support liner 13 surrounds the periphery being arranged on fuel pellet 11, and directly contact with fuel pellet 11, fuel rod clad 12 respectively, its cross sectional shape is wavy; Certainly, can be also other shapes, as zigzag, square-wave-shaped etc.In the present embodiment, this support liner 13 makes all-in-one-piece support liner 13 by one block of metal material, such as, directly bent by corrugated plate and surround circular, be arranged on the periphery of fuel pellet 11.Certainly, this support liner 13 also can be spliced by polylith metal material and form, or, make the support liner 13 of multistage, be arranged on the diverse location place between fuel pellet 11 and fuel rod clad 12 respectively.
As shown in Figure 4, be the schematic diagram of the support liner 13 of another kind of form, as shown in the figure, this support liner 13 is by polylith metallic material, the cross sectional shape of each block metal material is arc, and this profile design can better prevent fuel pellet 11 void swelling or reorientate after there is fragmentation.This support liner 13 is also provided with the inner liner support plate 18 directly contacting with fuel pellet 11 and connect, one end of curved support liner 13 directly contacts connection with fuel rod clad 12, the other end is fixedly connected with inner liner support plate 18, thus is connected between fuel pellet 11 and fuel rod clad 12 by whole support liner 13.Understandable, the two ends supporting liner 13 can directly connect with fuel rod clad 12 and fuel pellet 11 respectively.
The present invention, by supporting the setting of liner 13, can reduce pressure in fuel rod, hold more fission gas; The heat radiation to fuel pellet 11 can be strengthened, alleviate PCI phenomenon; All right reducing effect, in the strain energy of fuel rod clad 12, reduces risk PCI occurring and destroys.
Understandable, above embodiment only have expressed the preferred embodiment of the present invention, and it describes comparatively concrete and detailed, but therefore can not be interpreted as the restriction to the scope of the claims of the present invention; It should be pointed out that for the person of ordinary skill of the art, without departing from the inventive concept of the premise, can carry out independent assortment to above-mentioned technical characterstic, can also make some distortion and improvement, these all belong to protection scope of the present invention; Therefore, all equivalents of doing with the claims in the present invention scope and modification, all should belong to the covering scope of the claims in the present invention.
Claims (8)
1. a nuclear fuel rod, comprises fuel pellet and is arranged on the fuel rod clad of described fuel pellet periphery; It is characterized in that, described nuclear fuel rod also comprises the support liner be supported between described fuel pellet and fuel rod clad; Described support liner is made up of one or more metal material, and the cross sectional shape of each block metal material is arc; Described support liner also comprises the inner liner support plate directly contacting connection with described fuel pellet;
One end of described metal material directly contacts connection with described fuel rod clad, and the other end is fixedly connected with described inner liner support plate.
2. nuclear fuel rod according to claim 1, is characterized in that, described support liner is flexible liner.
3. nuclear fuel rod according to claim 2, is characterized in that, described support liner is arranged in the segment space between described fuel pellet and fuel rod clad, and is filled with helium in space between described fuel pellet and fuel rod clad.
4. the nuclear fuel rod according to any one of claims 1 to 3, is characterized in that, described support liner is arranged on the periphery of described fuel pellet.
5. nuclear fuel rod according to claim 4, is characterized in that, described metal material is pure zirconium, zircaloy or inconel.
6. nuclear fuel rod according to claim 4, is characterized in that, described support liner directly contacts with fuel rod clad with described fuel pellet simultaneously; The cross sectional shape of described support liner is wavy, zigzag or square-wave-shaped.
7. nuclear fuel rod according to claim 4, is characterized in that, described nuclear fuel rod also comprises upper end, lower end, the support column be arranged on described lower end, the holddown spring be arranged on described upper end;
Described fuel pellet is arranged between described holddown spring and support column, and described fuel rod clad is arranged between described upper end and lower end.
8. nuclear fuel rod according to claim 7, is characterized in that, described support liner is ring-type, is arranged on inside described fuel rod clad, for monoblock type or multistage split type.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210293447.3A CN102789820B (en) | 2012-08-17 | 2012-08-17 | Nuclear fuel rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210293447.3A CN102789820B (en) | 2012-08-17 | 2012-08-17 | Nuclear fuel rod |
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| Publication Number | Publication Date |
|---|---|
| CN102789820A CN102789820A (en) | 2012-11-21 |
| CN102789820B true CN102789820B (en) | 2015-04-22 |
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| CN201210293447.3A Active CN102789820B (en) | 2012-08-17 | 2012-08-17 | Nuclear fuel rod |
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Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103093838B (en) * | 2013-01-15 | 2014-07-23 | 西安交通大学 | Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same |
| CN105609147B (en) * | 2015-12-28 | 2017-09-12 | 中国原子能科学研究院 | A kind of system that helium tamponade is filled for fast reactor fuel rod |
| CN106078086B (en) * | 2016-06-12 | 2020-11-10 | 上海核工程研究设计院 | Zirconium alloy stainless steel composite tube for nuclear fuel element cladding and preparation method thereof |
| CN109801717B (en) * | 2019-03-20 | 2023-09-15 | 中国人民解放军国防科技大学 | Liquid lead bismuth cooling small-sized reactor fuel rod capable of reducing PCI effect |
| CN113409963A (en) * | 2021-06-17 | 2021-09-17 | 中国核动力研究设计院 | Fuel rod and fuel assembly for overcoming pellet cladding mechanical interaction |
| CN114121307A (en) * | 2021-11-23 | 2022-03-01 | 中国核动力研究设计院 | Composite cladding tube with internal buffer layer and fuel rod formed by composite cladding tube |
| CN114203314B (en) * | 2021-12-06 | 2022-12-09 | 西安交通大学 | Composite silicon carbide clad nuclear fuel rod with gap filled with liquid metal |
| CN114913997A (en) * | 2022-03-31 | 2022-08-16 | 中广核研究院有限公司 | Control rod and control rod assembly |
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| US4011134A (en) * | 1973-11-09 | 1977-03-08 | Kraftwerk Union Aktiengesellschaft | Pressurized-coolant reactor fuel rod |
| US4235673A (en) * | 1978-01-12 | 1980-11-25 | Combustion Engineering, Inc. | Chip sleeve for nuclear fuel elements |
| CN101567226A (en) * | 2008-03-24 | 2009-10-28 | 西屋电气有限责任公司 | Fuel rod and assembly containing an internal hydrogen/tritium getter structure |
| WO2011157780A1 (en) * | 2010-06-16 | 2011-12-22 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Solid interface joint with open porosity, for nuclear fuel rod |
| CN102568618A (en) * | 2010-12-14 | 2012-07-11 | 中国核动力研究设计院 | Uranium zirconium hydride nuclear fuel rod for power reactor |
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2012
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Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4011134A (en) * | 1973-11-09 | 1977-03-08 | Kraftwerk Union Aktiengesellschaft | Pressurized-coolant reactor fuel rod |
| US4235673A (en) * | 1978-01-12 | 1980-11-25 | Combustion Engineering, Inc. | Chip sleeve for nuclear fuel elements |
| CN101567226A (en) * | 2008-03-24 | 2009-10-28 | 西屋电气有限责任公司 | Fuel rod and assembly containing an internal hydrogen/tritium getter structure |
| WO2011157780A1 (en) * | 2010-06-16 | 2011-12-22 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Solid interface joint with open porosity, for nuclear fuel rod |
| CN102568618A (en) * | 2010-12-14 | 2012-07-11 | 中国核动力研究设计院 | Uranium zirconium hydride nuclear fuel rod for power reactor |
Non-Patent Citations (1)
| Title |
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| 法杰马第二代先进燃料组件;张凤林;《核动力工程》;19911031;第12卷(第5期);73-76页 * |
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| CN102789820A (en) | 2012-11-21 |
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Address after: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building, 15 Floor Patentee after: LING'AO NUCLEAR POWER Co.,Ltd. Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA GENERAL NUCLEAR POWER Corp. Address before: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building, 15 Floor Patentee before: LING'AO NUCLEAR POWER Co.,Ltd. Patentee before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. |
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Effective date of registration: 20160214 Address after: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building, 15 Floor Patentee after: LING'AO NUCLEAR POWER Co.,Ltd. Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. Address before: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13 Patentee before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. |
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| CP01 | Change in the name or title of a patent holder |
Address after: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building, 15 Floor Patentee after: LING'AO NUCLEAR POWER Co.,Ltd. Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA GENERAL NUCLEAR POWER Corp. Address before: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building, 15 Floor Patentee before: LING'AO NUCLEAR POWER Co.,Ltd. Patentee before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee before: CHINA GENERAL NUCLEAR POWER Corp. |