CN102974985A - Manufacture method for nuclear power station steam generator heat transfer tube end cap - Google Patents
Manufacture method for nuclear power station steam generator heat transfer tube end cap Download PDFInfo
- Publication number
- CN102974985A CN102974985A CN2012105135576A CN201210513557A CN102974985A CN 102974985 A CN102974985 A CN 102974985A CN 2012105135576 A CN2012105135576 A CN 2012105135576A CN 201210513557 A CN201210513557 A CN 201210513557A CN 102974985 A CN102974985 A CN 102974985A
- Authority
- CN
- China
- Prior art keywords
- steam generator
- generator heat
- sleeve
- transfer pipe
- sleeve blank
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 238000012546 transfer Methods 0.000 title claims abstract description 36
- 238000000034 method Methods 0.000 title claims abstract description 13
- 238000004519 manufacturing process Methods 0.000 title claims abstract description 11
- 238000003754 machining Methods 0.000 claims abstract description 8
- 238000012545 processing Methods 0.000 claims abstract description 5
- 239000000463 material Substances 0.000 claims description 18
- 239000006104 solid solution Substances 0.000 claims description 8
- 229910001069 Ti alloy Inorganic materials 0.000 claims description 5
- 229910001566 austenite Inorganic materials 0.000 claims description 5
- 239000013078 crystal Substances 0.000 claims description 5
- 238000007493 shaping process Methods 0.000 claims description 5
- 239000000243 solution Substances 0.000 claims description 5
- 239000010935 stainless steel Substances 0.000 claims description 4
- 229910001220 stainless steel Inorganic materials 0.000 claims description 4
- 238000010791 quenching Methods 0.000 claims description 3
- 230000000171 quenching effect Effects 0.000 claims description 3
- 238000005496 tempering Methods 0.000 claims description 3
- 230000015572 biosynthetic process Effects 0.000 claims description 2
- 230000007797 corrosion Effects 0.000 abstract description 7
- 238000005260 corrosion Methods 0.000 abstract description 7
- 238000003466 welding Methods 0.000 abstract description 7
- 238000005516 engineering process Methods 0.000 description 9
- 238000005242 forging Methods 0.000 description 7
- 238000002360 preparation method Methods 0.000 description 4
- 238000009434 installation Methods 0.000 description 3
- 230000032683 aging Effects 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 238000001514 detection method Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910045601 alloy Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000011900 installation process Methods 0.000 description 1
- 230000035800 maturation Effects 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 230000035882 stress Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Images
Abstract
The invention discloses a manufacture method for a nuclear power station steam generator heat transfer tube end cap. The manufacture method comprises the following steps of: respectively processing a taper-shaped sliding block and a sleeve blank in advance; putting the taper-shaped sliding block into the sleeve blank according to the requirement; then, carrying out diameter (rotary) swaging necking ton the sleeve blank; enabling the inner wall of the sleeve to form a conical surface fit with the taper-shaped sliding block; and finally, carrying out machining ton the excircle and the mouth part of the sleeve blank according to a drawing. The mechanical drawing end cap used for the nuclear power station steam generator heat transfer tube, which is prepared with the method, is free from a butt-welding welding line due to the fact that a drawing-type end cap is used, and has the advantages of good corrosion resistance, good use installability and long service life.
Description
Technical field
The invention belongs to the nuclear power technology field, relate to a kind of preparation for processing of nuclear power station steam generator heat-transfer pipe machinery plug.
Background technology
Nuclear power station mainly is comprised of nuclear reactor, steam generator, Turbo-generator Set three parts, the Main Function of steam generator is the water of the heat of water in the loop being passed to secondary circuit, and the bottom of steam generator evaporator section is to be made of inverted thousands of U-shaped heat-transfer pipes.The corrosion breakage of steam generator heat-transfer pipe is the principal element of nuclear power station unplanned shutdown and the loss of the station capacity factor always.In order to guarantee the reliability of steam generator in service, from that day of putting into operation, will follow the tracks of, assess the ruuning situation of steam generator, pinpoint the problems and will in time study, solve, the impurity that mainly contains steam generator heat-transfer pipe is removed and is being used as a servant detection, gets pipe, repairing bushing pipe and plugging etc.
China mostly is to introduce French technology or US Westinghouse company's technology in labour and at the nuclear power station of building at present, and its most of pipe fitting parts all are direct imported France or U.S.'s product, and the nuclear power station of particularly building last century is particularly like this.It is damaged that corrosion in use also often appears in the U-shaped heat exchanger tube of these steam generators at present, China has introduced the long-range multi frequency detection of MIZ-18A type system from U.S. ZETEC company specially its steam generator heat-transfer pipe has been implemented inservice inspection for this reason, according to testing result the damaged plugging of carrying out that exceeds the security clearance requirement of its corrosion is processed, the plug that at present plugging is used all is external imported product, and main supplier is US Westinghouse company.Two during the last ten years, and various countries have adopted different plugging technology, such as blast plugging, welding plugging and mechanical plugging.Blast plugging and welding plugging belong to permanent plugging or semipermanent plugging technology.The drawing type plug of machinery plugging easily takes out, and also can carry out bushing pipe or reuse under the premise that security is guaranteed the heat-transfer pipe that band damages the pipe that is blocked after the later technology maturation, therefore is widely adopted.
The common version of machinery drawing type plug as shown in Figure 1, this is a kind ofly to carry out plugging by the slide mode of extruding of inner cone core.This mechanical drawing type plug is divided into two parts: sleeve and cone core slide block, and for the consideration of processing and manufacturing, sleeve is divided into sleeve leading portion and sleeve latter end two parts usually, and after the tap web slide block was packed into, two sections welded together before and after the sleeve.Sleeve lining is designed to taper, during plugging, plug is packed in the steam generator heat-transfer pipe, pulling tap web slide block, sleeve generation radial plastic deformation, steam generator tube sheet generation strain, the residual stress that relies on distortion difference to cause reaches sealing effectiveness thereby sleeve outer wall and heat-transfer pipe inwall closely are adjacent to.
The process of above manufacturing machine drawing type plug in sleeve that the tap web slide block is packed into, needs in advance its sleeve to be processed as leading portion and back segment two parts, sleeve leading portion and back segment is carried out butt welding after waiting the tap web slide block to pack into.Although this method of manufacturing technology is simple, because there is weld seam in sleeve, in installation process, tears from the commissure easily and in use easily from the commissure corrosion failure, greatly affected result of use and the life-span of plug.
Summary of the invention
The object of the invention is to overcome the shortcoming of above-mentioned prior art, a kind of nuclear power station steam generator heat-transfer pipe plug manufacture method is provided, the nuclear power station steam generator heat-transfer pipe of the method preparation does not exist welding line with mechanical drawing type plug, corrosion resistance and good, good, the long service life of use installation capability.
The objective of the invention is to solve by the following technical programs:
This nuclear power station steam generator heat-transfer pipe plug manufacture method may further comprise the steps:
1) according to steam generator heat-transfer pipe material specification calculating machine drawing type plug size;
2) select the excellent base identical with the steam generator heat-transfer pipe material, according to corresponding material solid solution system excellent base is carried out solution treatment, make it to obtain single-phase austenite crystal tissue, then the structure according to sleeve blank is processed into type;
3) select titanium alloy or stainless steel spillikin base, with the structure machine-shaping of the spillikin base after solid solution+timeliness or the quenching+tempering processing according to cone core slide block;
4) pre-processed tap web slide block is packed in the pre-processed sleeve blank;
The sleeve blank that 5) will install the tap web slide block carries out the conical surface that the footpath is forged undergauge and sleeve lining formation and tap web slide block are fitted;
6) will directly forge at last sleeve blank cylindrical behind the undergauge and oral area carries out machining and obtains the heat-transfer pipe plug.
Further, above-mentioned steps 2) in, excellent base length is longer than the finished product plug, and diameter is more than 1.5 times of finished product plug.
The present invention has following beneficial effect:
The present invention processes respectively conical sliding block and sleeve blank in advance, with the conical sliding block sleeve blank of packing on request, then sleeve blank is carried out footpath (revolving) and forge undergauge and make sleeve lining form the conical surface that fits with the cone slide block, according to drawing sleeve blank cylindrical and oral area are carried out machining at last.Adopt the nuclear power station steam generator heat-transfer pipe of the method preparation not exist welding line with mechanical drawing type plug, corrosion resistance and good, good, the long service life of use installation capability.
Description of drawings
Fig. 1 is mechanical drawing type plug common structure form figure;
Fig. 2 is the present invention's machinery drawing type stopper structure figure;
Fig. 3 is sleeve blank structure chart of the present invention;
Fig. 4 is tap web slide block structure figure of the present invention;
Fig. 5 is tap web slide block of the present invention-sleeve blank installation diagram;
Fig. 6 is that the necking down schematic diagram is forged in the present invention footpath (revolving);
Fig. 7 is blank figure after the forging necking down of the present invention footpath (revolving);
Fig. 8 is final products machining sketch chart of the present invention;
Fig. 9 is that specification is Φ 19.06 * 1.09 heat-transfer pipes with mechanical drawing type stopper structure figure in the embodiment of the invention;
Figure 10 is that specification is Φ 15 * 1.2 heat-transfer pipes with mechanical drawing type stopper structure figure in the embodiment of the invention.
The specific embodiment
Below in conjunction with accompanying drawing the present invention is done and to describe in further detail:
The material that sleeve of the present invention adopts is consistent with nuclear power station steam generator heat-transfer pipe material therefor, is generally the alloys such as 0Cr15Ni75Fe, 0Cr30Ni60Fe10, Cr20Ni32; The present invention bores the core slide block and generally adopts the relatively high titanium alloy material of hardness or stainless steel material.The present invention proposes a kind of nuclear reactor steam generator heat-transfer pipe and navigates with mechanical drawing type plug preparation method, may further comprise the steps:
1) calculates mechanical drawing type plug size according to steam generator heat-transfer pipe material specification, seen Fig. 2.
2) (excellent base length slightly is longer than the finished product plug to select the excellent base identical with the steam generator heat-transfer pipe material, diameter is more than 1.5 times of finished product plug), according to corresponding material solid solution system excellent base is carried out solution treatment, make it to obtain single-phase austenite crystal tissue, then be processed into type according to sleeve blank figure, see Fig. 3.
3) select relatively high titanium alloy or the stainless steel spillikin base of hardness, the spillikin base after solid solution+timeliness (or quenching+tempering) is processed is seen Fig. 4 according to the machine-shaping of cone core slide block drawing.
4) pre-processed tap web slide block is packed in the pre-processed sleeve blank, see Fig. 5.
The sleeve that 5) will install the tap web slide block carries out footpath (revolving) forging undergauge and makes sleeve lining form the conical surface that fits with the cone slide block, sees Fig. 6, Fig. 7.
6) carry out machining according to sleeve blank cylindrical and oral area behind drawing general footpath (revolving) the forging undergauge at last, see Fig. 8.
Further detailed technology contents of the present invention below by way of embodiments and drawings:
Embodiment 1
Specification Φ 19.06 * 1.09, material 0Cr15Ni75Fe heat-transfer pipe prepare with mechanical drawing type plug
1) calculates mechanical drawing type plug size (external diameter Φ 16) according to steam generator heat-transfer pipe material specification, seen Fig. 2.
2) select 0Cr15Ni75Fe rod base (the excellent base length 115mm identical with the steam generator heat-transfer pipe material, diameter is 25mm), blank was carried out solution treatment in 2 hours 1050 ℃ of insulations, make it to obtain single-phase austenite crystal tissue, then be processed into type according to sleeve blank figure, see Fig. 3.
3) select the relatively high TC11 titanium alloy spillikin base of hardness, the spillikin base after solid solution+Ageing Treatment according to the machine-shaping of cone core slide block drawing, is seen Fig. 4.
4) pre-processed tap web slide block is packed in the pre-processed sleeve blank, see Fig. 5.
The sleeve that 5) will install the tap web slide block carries out footpath (revolving) forging undergauge and makes sleeve lining form the conical surface (5 ° of single face taperings) that fits with the cone slide block, sees Fig. 6, Fig. 7.
6) carry out machining according to sleeve blank cylindrical and oral area behind drawing general footpath (revolving) the forging undergauge at last, see Fig. 8, Fig. 9.
Embodiment 2
Specification Φ 15 * 1.2, material C r20Ni32 heat-transfer pipe prepare with mechanical drawing type plug
1) calculates mechanical drawing type plug size (external diameter Φ 12) according to steam generator heat-transfer pipe material specification, seen Fig. 2.
2) select Cr20Ni32 rod base (the excellent base length 80mm identical with the steam generator heat-transfer pipe material, diameter is 18mm), blank was carried out solution treatment in 2 hours 1050 ℃ of insulations, make it to obtain single-phase austenite crystal tissue, then be processed into type according to sleeve blank figure, see Fig. 3.
3) select the relatively high 1Cr18Ni9Ti spillikin base of hardness, the spillikin base after solid solution+Ageing Treatment according to the machine-shaping of cone core slide block drawing, is seen Fig. 4.
4) pre-processed tap web slide block is packed in the pre-processed sleeve blank, see Fig. 5.
The sleeve that 5) will install the tap web slide block carries out footpath (revolving) forging undergauge and makes sleeve lining form the conical surface (5 ° of single face taperings) that fits with the cone slide block, sees Fig. 6, Fig. 7.
6) carry out machining according to sleeve blank cylindrical and oral area behind drawing general footpath (revolving) the forging undergauge at last, see Fig. 8, Figure 10.
Claims (2)
1. a nuclear power station steam generator heat-transfer pipe plug manufacture method is characterized in that, may further comprise the steps:
1) according to steam generator heat-transfer pipe material specification calculating machine drawing type plug size;
2) select the excellent base identical with the steam generator heat-transfer pipe material, according to corresponding material solid solution system excellent base is carried out solution treatment, make it to obtain single-phase austenite crystal tissue, then the structure according to sleeve blank is processed into type;
3) select titanium alloy or stainless steel spillikin base, with the structure machine-shaping of the spillikin base after solid solution+timeliness or the quenching+tempering processing according to cone core slide block;
4) pre-processed tap web slide block is packed in the pre-processed sleeve blank;
The sleeve blank that 5) will install the tap web slide block carries out the conical surface that the footpath is forged undergauge and sleeve lining formation and tap web slide block are fitted;
6) will directly forge at last sleeve blank cylindrical behind the undergauge and oral area carries out machining and obtains the heat-transfer pipe plug.
2. nuclear power station steam generator heat-transfer pipe plug manufacture method according to claim 1 is characterized in that step 2) in, excellent base length is longer than the finished product plug, and diameter is more than 1.5 times of finished product plug.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210513557.6A CN102974985B (en) | 2012-12-03 | 2012-12-03 | A kind of nuclear power station steam generator heat transfer tube end cap manufacture method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210513557.6A CN102974985B (en) | 2012-12-03 | 2012-12-03 | A kind of nuclear power station steam generator heat transfer tube end cap manufacture method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN102974985A true CN102974985A (en) | 2013-03-20 |
| CN102974985B CN102974985B (en) | 2015-11-04 |
Family
ID=47849490
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210513557.6A Active CN102974985B (en) | 2012-12-03 | 2012-12-03 | A kind of nuclear power station steam generator heat transfer tube end cap manufacture method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102974985B (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103737264A (en) * | 2013-12-25 | 2014-04-23 | 西安西工大超晶科技发展有限责任公司 | Roll expanding type mechanical plug for nuclear power station vapor generator heat transfer pipe and manufacturing method thereof |
| CN103737263A (en) * | 2013-12-25 | 2014-04-23 | 西安西工大超晶科技发展有限责任公司 | Roller expansion type mechanical plug for heat transfer tube of steam generator and manufacturing method thereof |
| CN103894791A (en) * | 2014-02-19 | 2014-07-02 | 中国寰球工程公司 | Technology for manufacturing heat transfer enhancing component in heat exchange tube provided with heat transfer enhancing component |
| CN104501855A (en) * | 2014-12-15 | 2015-04-08 | 钢铁研究总院 | Sample device and method for testing tube-plugging effect of heat-transferring tube of vapor generator |
| CN105798542A (en) * | 2014-12-31 | 2016-07-27 | 国核电站运行服务技术有限公司 | Machining method for plug in heat transfer pipe of heat exchanger |
| CN106755770A (en) * | 2016-11-25 | 2017-05-31 | 西安诺博尔稀贵金属材料有限公司 | The processing method for improving Austenitic stainless steel pipe material inner surface quality |
| CN107290075A (en) * | 2017-07-31 | 2017-10-24 | 久茂自动化(大连)有限公司 | Abrasion resistant thermocouple processing method and abrasion resistant thermocouple |
| CN110836615A (en) * | 2018-08-17 | 2020-02-25 | 清华大学 | Method for blocking heat exchange tube |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0404637A1 (en) * | 1989-06-23 | 1990-12-27 | Framatome | Sealing plug for a steam generator tube |
| US5456290A (en) * | 1989-11-20 | 1995-10-10 | Westinghouse Electric Corporation | Tube plug having a flange sealing a chamber for plugging a tubular member |
| CN2637027Y (en) * | 2003-08-01 | 2004-09-01 | 王春廷 | Extrusion equipment for making pipe end changing size |
| CN101607279A (en) * | 2009-07-23 | 2009-12-23 | 宁波安拓实业有限公司 | The multistation cold extrusion forming method of powerful gecko pipe |
-
2012
- 2012-12-03 CN CN201210513557.6A patent/CN102974985B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0404637A1 (en) * | 1989-06-23 | 1990-12-27 | Framatome | Sealing plug for a steam generator tube |
| US5456290A (en) * | 1989-11-20 | 1995-10-10 | Westinghouse Electric Corporation | Tube plug having a flange sealing a chamber for plugging a tubular member |
| CN2637027Y (en) * | 2003-08-01 | 2004-09-01 | 王春廷 | Extrusion equipment for making pipe end changing size |
| CN101607279A (en) * | 2009-07-23 | 2009-12-23 | 宁波安拓实业有限公司 | The multistation cold extrusion forming method of powerful gecko pipe |
Non-Patent Citations (2)
| Title |
|---|
| 闫国华等: "蒸汽发生器堵头设计与堵管研究", 《压力容器》, no. 02, 28 February 2011 (2011-02-28) * |
| 魏清海等: "核电站蒸汽发生器传热管堵管工艺研究", 《设备管理与维修》, no. 02, 28 February 2012 (2012-02-28) * |
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103737264A (en) * | 2013-12-25 | 2014-04-23 | 西安西工大超晶科技发展有限责任公司 | Roll expanding type mechanical plug for nuclear power station vapor generator heat transfer pipe and manufacturing method thereof |
| CN103737263A (en) * | 2013-12-25 | 2014-04-23 | 西安西工大超晶科技发展有限责任公司 | Roller expansion type mechanical plug for heat transfer tube of steam generator and manufacturing method thereof |
| CN103737264B (en) * | 2013-12-25 | 2016-03-02 | 西安西工大超晶科技发展有限责任公司 | A kind of nuclear power station steam generator heat-transfer pipe roller expanding mechanical plug and manufacture method thereof |
| CN103894791A (en) * | 2014-02-19 | 2014-07-02 | 中国寰球工程公司 | Technology for manufacturing heat transfer enhancing component in heat exchange tube provided with heat transfer enhancing component |
| CN104501855A (en) * | 2014-12-15 | 2015-04-08 | 钢铁研究总院 | Sample device and method for testing tube-plugging effect of heat-transferring tube of vapor generator |
| CN105798542A (en) * | 2014-12-31 | 2016-07-27 | 国核电站运行服务技术有限公司 | Machining method for plug in heat transfer pipe of heat exchanger |
| CN105798542B (en) * | 2014-12-31 | 2018-06-01 | 国核电站运行服务技术有限公司 | The processing method of plug in a kind of heat transfering tube of heat exchanger |
| CN106755770A (en) * | 2016-11-25 | 2017-05-31 | 西安诺博尔稀贵金属材料有限公司 | The processing method for improving Austenitic stainless steel pipe material inner surface quality |
| CN107290075A (en) * | 2017-07-31 | 2017-10-24 | 久茂自动化(大连)有限公司 | Abrasion resistant thermocouple processing method and abrasion resistant thermocouple |
| CN107290075B (en) * | 2017-07-31 | 2023-05-23 | 久茂自动化(大连)有限公司 | Wear-resistant thermocouple processing method and wear-resistant thermocouple |
| CN110836615A (en) * | 2018-08-17 | 2020-02-25 | 清华大学 | Method for blocking heat exchange tube |
Also Published As
| Publication number | Publication date |
|---|---|
| CN102974985B (en) | 2015-11-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102974985A (en) | Manufacture method for nuclear power station steam generator heat transfer tube end cap | |
| CN204051658U (en) | A kind of hydrogenation reactor | |
| US8640337B2 (en) | Pipe expansion method | |
| CN103143659B (en) | Hollow forging method of nuclear power main pipeline | |
| CN104174798B (en) | Main nuclear power pipeline pipe short route forging method | |
| CN204881317U (en) | Steam generator's end cap and steam generator | |
| CN104353973A (en) | Preparation method of austenitic stainless steel pipe | |
| JP2011073059A (en) | Method of manufacturing metallic double pipe | |
| CN103861888A (en) | Preparation method for high-performance copper/titanium composite pipe | |
| JP5472480B2 (en) | Manufacturing method of double pipe with braided wire | |
| CN103555915A (en) | Device for performing heat treatment correction on titanium alloy spoke structure welded case | |
| CN104014928A (en) | Dissimilar steel welding method for martensite heat-resisting steel and austenitic heat-resisting steel | |
| CN102773398A (en) | Method for forging slender and thick-walled pipe fittings | |
| CN105290554B (en) | A kind of vacuum brazing technique of niobium tungsten alloy and stainless steel ring-shaped work pieces | |
| CN106001825A (en) | Connecting method for corrosion-resistant high-temperature alloy pipe and corrosion-resistant high-temperature pipe plate and heat exchanger | |
| CN203718276U (en) | Drawing core expansion type mechanical end cap for heat transfer pipe | |
| CN103500590B (en) | High temperature gas cooled reactor Helium fan connection structure for inlet | |
| CN101439385A (en) | Drill rocker end upsetting method | |
| CN204922353U (en) | External fixation festival in steel bushing steel steam direct -burried pipeline | |
| CN104534453B (en) | A kind of cold wall type High Temperature High Pressure superheater | |
| CN108728623B (en) | Heat treatment anti-deformation device for combined double-tube-plate threaded locking ring heat exchanger and use method thereof | |
| CN203948802U (en) | A kind of composite bimetal pipe | |
| CN101907288B (en) | Structure transiting from high-temperature heat exchange tube material to pressure container shell material | |
| CN204350340U (en) | Flange form heater | |
| CN105798542B (en) | The processing method of plug in a kind of heat transfering tube of heat exchanger |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CB03 | Change of inventor or designer information |
Inventor after: Zhang Lijun Inventor after: Liao Changbin Inventor after: Xue Xiangyi Inventor after: Hu Huihua Inventor after: Li Jinshan Inventor after: Gong Weimin Inventor after: Cheng Tan Inventor after: Zhou Zhongbo Inventor after: Shao Bo Inventor before: Zhang Lijun Inventor before: Hu Rui Inventor before: Zhou Zhongbo Inventor before: Xue Xiangyi Inventor before: Chang Hui Inventor before: Bai Yu Inventor before: Zhu Pengchao Inventor before: Wang Xingyun |
|
| CB03 | Change of inventor or designer information | ||
| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20170728 Address after: 710016 No. seven, 92 Fengcheng Road, Xi'an economic and Technological Development Zone, Shaanxi, China Co-patentee after: RESEARCH INSTITUTE OF NUCLEAR POWER OPERATION Patentee after: XI'AN SUPERCRYSYAL SCI-TECH DEVELOPMENT Co.,Ltd. Co-patentee after: CHINA NUCLEAR POWER OPERATION TECHNOLOGY Corp.,Ltd. Address before: 710016 Xi'an economic and Technological Development Zone, Fengcheng, China, No. seven road, Shaanxi Patentee before: XI'AN SUPERCRYSYAL SCI-TECH DEVELOPMENT Co.,Ltd. |
|
| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: 710016 No.92, Fengcheng 7th Road, Xi'an Economic and Technological Development Zone, Shaanxi Province Patentee after: Xi'an Supercrystalline Technology Co.,Ltd. Patentee after: RESEARCH INSTITUTE OF NUCLEAR POWER OPERATION Patentee after: CHINA NUCLEAR POWER OPERATION TECHNOLOGY Corp.,Ltd. Address before: 710016 No.92, Fengcheng 7th Road, Xi'an Economic and Technological Development Zone, Shaanxi Province Patentee before: XI'AN SUPERCRYSYAL SCI-TECH DEVELOPMENT Co.,Ltd. Patentee before: RESEARCH INSTITUTE OF NUCLEAR POWER OPERATION Patentee before: CHINA NUCLEAR POWER OPERATION TECHNOLOGY Corp.,Ltd. |
|
| CP02 | Change in the address of a patent holder | ||
| CP02 | Change in the address of a patent holder |
Address after: 710299 No. 10, East Section of Jinggao North Road, Jingwei New City, Xi'an Economic and Technological Development Zone, Shaanxi Province Patentee after: Xi'an Supercrystalline Technology Co.,Ltd. Patentee after: RESEARCH INSTITUTE OF NUCLEAR POWER OPERATION Patentee after: CHINA NUCLEAR POWER OPERATION TECHNOLOGY Corp.,Ltd. Address before: 710016 No.92, Fengcheng 7th Road, Xi'an Economic and Technological Development Zone, Shaanxi Province Patentee before: Xi'an Supercrystalline Technology Co.,Ltd. Patentee before: RESEARCH INSTITUTE OF NUCLEAR POWER OPERATION Patentee before: CHINA NUCLEAR POWER OPERATION TECHNOLOGY Corp.,Ltd. |