CN102789820A - Nuclear fuel rod - Google Patents
Nuclear fuel rod Download PDFInfo
- Publication number
- CN102789820A CN102789820A CN2012102934473A CN201210293447A CN102789820A CN 102789820 A CN102789820 A CN 102789820A CN 2012102934473 A CN2012102934473 A CN 2012102934473A CN 201210293447 A CN201210293447 A CN 201210293447A CN 102789820 A CN102789820 A CN 102789820A
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- fuel rod
- fuel
- pellet
- 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 the nuclear power station presurized water reactor.
Background technology
In service at nuclear power plant reactor, the breakage of nuclear fuel rod is discharged in the coolant system of reactor the radioactive fission product in the nuclear fuel rod, thereby jeopardizes the normal operation of nuclear power station.PCI is one of potential destructive factor of nuclear fuel rod.PCI or PCMI are exactly the abbreviation of English Pellet-Cladding Mechanical Interaction, refer to fuel pellet and the involucrum mechanical interaction in the nuclear power station operational process.
Usually, nuclear fuel rod comprises fuel pellet and is arranged on the peripheral fuel rod clad of fuel pellet etc.There is certain primary clearance between fuel rod clad and fuel pellet, in the gap, is full of helium (He gas) and presses as heat eliminating medium and in providing with the suffered external pressure of balance fuel rod involucrum.
Along with the intensification of operation burnup, solid fission product and gas fission product in the fuel pellet are taken in a large number in fuel pellet, make fuel pellet generation void swelling, and fuel pellet diameter increases.Fuel pellet ftractures under the effect of high temperature difference simultaneously, causes the reorientation of fuel pellet, and the 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 of neutron and reactor, under the effect of cooling medium hydraulic pressure, radially produces the creep contraction, and the internal diameter of fuel rod clad is reduced.
And fuel pellet and fuel rod clad are material different, and the thermal expansion of fuel pellet is greater than fuel rod clad.In the operational process, the temperature of fuel pellet is higher than the medial temperature of involucrum far away in heap, and the thermal expansion amount of fuel pellet is much higher than the thermal expansion amount of fuel rod clad like this.
Therefore, under the synergy of void swelling, thermal expansion and the inside creep of fuel rod clad, along with the intensification of fuel-assembly burn-up, the diametric clearance of fuel rod clad and fuel pellet reduces until closure, and PCI takes place.
Because the risk that exists PCI to destroy, in service at nuclear power station, nuclear power station just can not exceed operating standard fast lifting reactor capability, low power run for a long time.The fuel pellet temperature raises rapidly and rapid expanding in the process of fast lifting reactor capability; Make the thermal expansion of fuel rod clad and the thermal expansion that outside creep has little time to offset fuel pellet; Thereby the stress that involucrum is born surpasses the yield strength of involucrum, causes fuel rod clad to destroy because of PCI.
Reducing fast in the process of reactor capability; Because the motion of control rod, the axial power of reactor distribute and become unusual, make the partial power of nuclear fuel rod be much higher than average power; Produce the phenomenon identical, cause fuel rod clad to destroy because of PCI with fast lifting power.
Nuclear power plant reactor moves under low-power for a long time, and the pressure in the nuclear fuel rod is well below the operating pressure of reactor-loop, and this has aggravated fuel rod clad because the inside creep of effect of external pressure; The gap of involucrum and pellet is reduced; Cause fuel pellet to contact in advance,, increased the stressed load of involucrum in case reactor capability changes with fuel rod clad; Increase the risk that PCI destroys, thereby caused fuel rod clad that nuclear leakage takes place because of PCI destroys.
Existing nuclear fuel rod can't adapt to the risk that above-mentioned PCI destroys, and operation has brought uncertainty to nuclear plant safety.
Summary of the invention
The technical matters that the present invention will solve is, provides a kind of and can effectively alleviate the nuclear fuel rod that PCI destroys.
The technical solution adopted for the present invention to solve the technical problems is: construct a kind of nuclear fuel rod, comprise fuel pellet and be arranged on the peripheral fuel rod clad of said fuel pellet; Said nuclear fuel rod also comprises the support liner that is supported between said fuel pellet and the fuel rod clad.
In nuclear fuel rod of the present invention, said support liner is a flexible liner.
In nuclear fuel rod of the present invention, said support liner is arranged in the segment space between said fuel pellet and the fuel rod clad, and is filled with helium in the space between said fuel pellet and fuel rod clad.
In nuclear fuel rod of the present invention, said support liner is processed by one or more metal material, is arranged on the periphery of said fuel pellet.
In nuclear fuel rod of the present invention, said metal material is pure zirconium, zircaloy or inconel.
In nuclear fuel rod of the present invention, said support liner directly contacts with fuel rod clad with said fuel pellet simultaneously; The cross sectional shape of said support liner is wavy, zigzag or square wave shape.
In nuclear fuel rod of the present invention, said support liner is processed by the polylith metal material, and the cross sectional shape of each piece metal material is an arc.
In nuclear fuel rod of the present invention, said support liner also comprises with said fuel pellet and directly contacts the liner back up pad that is connected;
One end of said metal material directly contacts with said fuel rod clad and is connected, and the other end is fixedly connected with said liner back up pad.
In nuclear fuel rod of the present invention, said nuclear fuel rod also comprises upper end, lower end, be arranged on support column on the said lower end, be arranged on the holddown spring on the said upper end;
Said fuel pellet is installed between said holddown spring and the support column, and said fuel rod clad is installed between said upper end and the lower end.
In nuclear fuel rod of the present invention, said support liner is a ring-type, and it is inboard to be arranged on said fuel rod clad, for monoblock type or multistage split type.
Embodiment of the present invention has following beneficial effect: through the support liner is set between fuel pellet and fuel rod clad; Can reduce the interior pressure of nuclear fuel rod, hold more fission gas, can strengthen heat radiation fuel pellet; Alleviate the PCI phenomenon; Can also reduce the strain energy that acts on fuel rod clad, reduce the risk that PCI destroys takes place, improve the security of nuclear power plant reactor operation greatly.
Description of drawings
To combine accompanying drawing and embodiment that the present invention is described further below, in the accompanying drawing:
Fig. 1 is the structural representation of an embodiment of nuclear fuel rod of the present invention;
Fig. 2 is the schematic cross-section of an embodiment of nuclear fuel rod of the present invention;
Fig. 3 is that nuclear fuel rod of the present invention adopts waveform to support the synoptic diagram of liner;
Fig. 4 is that nuclear fuel rod of the present invention adopts arc to support the synoptic diagram of liner.
Embodiment
Like Fig. 1, shown in 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 upper end 14, lower end 15, be arranged on support column 16 on the lower end 15, be arranged on the installing mechanisms such as holddown spring 17 on the upper end 14, is used for fixing fuel pellet 11 and fuel rod clad 12 are installed; Certainly, installing mechanism also can adopt other forms of mounting structure.
As shown in the figure; This fuel pellet 11 is installed between holddown spring 17 and the support column 16; And fuel rod clad 12 is installed between upper end 14 and the lower end 15, between fuel rod clad 12 and fuel chip, forms the gap, supports liner 13 and is arranged in the gap; And contact with fuel rod clad 12 with fuel pellet 11, play a supporting role.Can select for use solid material to process owing to support liner 13; Can be arranged in the segment space between fuel pellet 11 and the fuel rod clad 12; Because its thermal conductivity far is higher than the helium in the fuel rod, can strengthen the heat radiation to fuel pellet 11, suppress fuel pellet 11 overexpansions.In addition, can also further be filled with helium in the space between fuel pellet 11 and fuel rod clad 12.
This support liner 13 can be selected flexible liner for use, can the elastic potential energy that the strain energy that directly act on fuel rod clad 12 inwalls converts flexible liner to be stored, and fuel rod clad 12 is implemented buffering, makes it be difficult for wrecking.
This support liner 13 can be processed by the very little solid material of thermal neutron absorption cross section, and selecting this type of material for use is in order to guarantee the neutron economy property in the reactor.In the present embodiment, it is the flexible liner material that this support liner 13 is selected pure zirconium for use, and the thermal neutron absorption cross section of pure zirconium is very little, is about 0.185b (1b=1 * 10
-28m
2), can guarantee enough neutron economy property in the anti-heap.In addition, pure zirconium phase transition temperature is 862 ℃.Under worst two types of transient states, the linear power density of fuel is no more than 400KW/cm when nuclear power station moves, and corresponding therewith fuel pellet 11 surface temperatures are about 450 ℃, far below the phase transition temperature of pure zirconium.Therefore under the most abominable two types of transient states; The support liner of being processed by pure zirconium 13 still has suitable elasticity and intensity; At this moment, supporting liner 13 still can provide supporting to prevent that it from caving in to fuel rod clad 12, and can store the mechanical energy that pellet expands through elastic deformation; Fuel rod clad 12 is implemented buffering, cushioned the interaction energy of pellet greatly involucrum.
Certainly, support liner 13 and can also select for use other material to make, for example the material commonly used such as zircaloy, inconel in the nuclear power field.
Supporting liner 13 is solid, and its thermal conductivity far is greater than He gas.For example; Pure zirconium thermal conductivity is 0.227W/cmK; Be about 150 times of He (0.00152W/cmK); Surface radiating that can efficient hardening fuel pellet 11 reduces fuel pellet 11 surface temperatures and also suppresses its whole overexpansion, can significantly reduce fuel pellet 11 because of thermal expansion to supporting the stress that liner 13 and fuel rod clad 12 apply.Further, this length that supports liner 13 need surpass the length of the active section of fuel pellet 11, thereby can better heat be derived.
In addition; Needn't charge into too much He gas in the nuclear fuel rod and (be used for balance fuel rod involucrum 12 suffered external pressures to keep thermal conductivity and interior pressure; This external pressure is from light water coolant), just can hold more fission gas in the nuclear fuel rod like this, make nuclear fuel rod can reach higher burnup.
This support liner 13 can be done circlewise; All contact with fuel rod clad 12 with fuel pellet 11; Therefore can fuel rod clad 12 suffered external pressures be passed to fuel pellet 11; Hard fuel pellet 11 can become the support of fuel rod clad 12, prevents fuel rod clad 12 and caves in toward fuel pellet 11 directions because at high temperature receive the external force place creep, causes contacting of fuel rod clad 12 and fuel pellet 11; Support the act as a fuel barrier of excellent involucrum 12 of liner 13, 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 perhaps fragmentation takes place descends.Fuel pellet 11 directly contacts with support liner 13; Even because strain energy is excessive or fission product pollution initiation stress corrosion causes supporting liner 13 generation rupture failures; This damage effect can not be delivered to fuel rod clad 12 yet, and supporting 13 pairs of fuel rod clad 12 of liner is expendable barriers.
As shown in Figure 3, this support liner 13 surrounds the periphery that is arranged on fuel pellet 11, directly contacts with fuel pellet 11, fuel rod clad 12 respectively, and its cross sectional shape is wavy; Certainly, also can be other shapes, like zigzag, square wave shape etc.In the present embodiment, this support liner 13 is processed all-in-one-piece support liner 13 by a metal material, for example by corrugated plate directly bending surround circularly, be arranged on the periphery of fuel pellet 11.Certainly, this supports liner 13 also can be made up of the splicing of polylith metal material, perhaps, makes the support liner 13 of multistage, is installed in the diverse location place between fuel pellet 11 and the fuel rod clad 12 respectively.
As shown in Figure 4; Be the synoptic diagram of the support liner 13 of another kind of form, as shown in the figure, this supports liner 13 and is supported by the polylith metal material; The cross sectional shape of each piece metal material is an arc, and this shaped design can better prevent fuel pellet 11 void swellings or take place to reorientate after the fragmentation.This support liner 13 also is provided with fuel pellet 11 and directly contacts the liner back up pad 18 that is connected; The end that arc supports liner 13 is connected with fuel rod clad 12 direct contacts; The other end is fixedly connected with liner back up pad 18, thereby whole support liner 13 is connected between fuel pellet 11 and the fuel rod clad 12.Understandable, the two ends of supporting liner 13 can directly join with fuel rod clad 12 and fuel pellet 11 respectively.
The present invention can reduce in the fuel rod and press through supporting the setting of liner 13, holds more fission gas; Can strengthen heat radiation, alleviate the PCI phenomenon fuel pellet 11; Can also reduce the strain energy that acts on fuel rod clad 12, reduce the risk that PCI destroys takes place.
Understandable, above embodiment has only expressed preferred implementation of the present invention, and it describes comparatively concrete and detailed, but can not therefore be interpreted as the restriction to claim of the present invention; Should be pointed out that for the person of ordinary skill of the art, under the prerequisite that does not break away from the present invention's design, 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 and modifications of being done with claim scope of the present invention all should belong to the covering scope of claim of the present invention.
Claims (10)
1. a nuclear fuel rod comprises fuel pellet and is arranged on the peripheral fuel rod clad of said fuel pellet; It is characterized in that said nuclear fuel rod also comprises the support liner that is supported between said fuel pellet and the fuel rod clad.
2. nuclear fuel rod according to claim 1 is characterized in that, said support liner is a flexible liner.
3. nuclear fuel rod according to claim 2 is characterized in that, said support liner is arranged in the segment space between said fuel pellet and the fuel rod clad, and is filled with helium in the space between said fuel pellet and fuel rod clad.
4. according to each described nuclear fuel rod of claim 1 to 3, it is characterized in that said support liner is processed by one or more metal material, is arranged on the periphery of said fuel pellet.
5. nuclear fuel rod according to claim 4 is characterized in that, said metal material is pure zirconium, zircaloy or inconel.
6. nuclear fuel rod according to claim 4 is characterized in that, said support liner directly contacts with fuel rod clad with said fuel pellet simultaneously; The cross sectional shape of said support liner is wavy, zigzag or square wave shape.
7. nuclear fuel rod according to claim 4 is characterized in that, said support liner is processed by the polylith metal material, and the cross sectional shape of each piece metal material is an arc.
8. nuclear fuel rod according to claim 7 is characterized in that, said support liner also comprises with said fuel pellet and directly contacts the liner back up pad that is connected;
One end of said metal material directly contacts with said fuel rod clad and is connected, and the other end is fixedly connected with said liner back up pad.
9. nuclear fuel rod according to claim 4 is characterized in that, said nuclear fuel rod also comprises upper end, lower end, be arranged on support column on the said lower end, be arranged on the holddown spring on the said upper end;
Said fuel pellet is installed between said holddown spring and the support column, and said fuel rod clad is installed between said upper end and the lower end.
10. nuclear fuel rod according to claim 9 is characterized in that, said support liner is a ring-type, and it is inboard to be arranged on said 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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN102789820A true CN102789820A (en) | 2012-11-21 |
| CN102789820B CN102789820B (en) | 2015-04-22 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210293447.3A Active CN102789820B (en) | 2012-08-17 | 2012-08-17 | Nuclear fuel rod |
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| CN (1) | CN102789820B (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103093838A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same |
| CN105609147A (en) * | 2015-12-28 | 2016-05-25 | 中国原子能科学研究院 | System for helium charging and plug pressing of fuel rods of fast reactor |
| CN106078086A (en) * | 2016-06-12 | 2016-11-09 | 上海核工程研究设计院 | A kind of Reactor fuel element cladding zircaloy stainless steel composite pipe and preparation method thereof |
| CN109801717A (en) * | 2019-03-20 | 2019-05-24 | 中国人民解放军国防科技大学 | Fuel rod for liquid lead bismuth cooling small reactor for 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 |
| CN114203314A (en) * | 2021-12-06 | 2022-03-18 | 西安交通大学 | Composite silicon carbide clad nuclear fuel rod with gap filled with liquid metal |
| WO2023184891A1 (en) * | 2022-03-31 | 2023-10-05 | 中广核研究院有限公司 | Control rod and control rod assembly |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103093838A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same |
| 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 |
| CN105609147A (en) * | 2015-12-28 | 2016-05-25 | 中国原子能科学研究院 | System for helium charging and plug pressing of fuel rods of fast reactor |
| CN106078086A (en) * | 2016-06-12 | 2016-11-09 | 上海核工程研究设计院 | A kind of Reactor fuel element cladding zircaloy stainless steel composite pipe and preparation method thereof |
| 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 |
| CN109801717A (en) * | 2019-03-20 | 2019-05-24 | 中国人民解放军国防科技大学 | Fuel rod for liquid lead bismuth cooling small reactor for reducing PCI effect |
| 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 |
| CN114203314A (en) * | 2021-12-06 | 2022-03-18 | 西安交通大学 | Composite silicon carbide clad nuclear fuel rod with gap filled with liquid metal |
| 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 |
| WO2023184891A1 (en) * | 2022-03-31 | 2023-10-05 | 中广核研究院有限公司 | Control rod and control rod assembly |
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| CN102789820B (en) | 2015-04-22 |
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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. |