CN101577145A - Mounting method for insulating layer of nuclear reactor pressure vessel - Google Patents
Mounting method for insulating layer of nuclear reactor pressure vessel Download PDFInfo
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- CN101577145A CN101577145A CNA2008100671068A CN200810067106A CN101577145A CN 101577145 A CN101577145 A CN 101577145A CN A2008100671068 A CNA2008100671068 A CN A2008100671068A CN 200810067106 A CN200810067106 A CN 200810067106A CN 101577145 A CN101577145 A CN 101577145A
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- insulation layer
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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 relates to a mounting method for an insulating layer of a nuclear reactor pressure vessel. In order to optimize the whole nuclear island mounting construction period, in the mounting method, a connecting ring, a hanging bracket, a channel steel ring, a barrel insulated board, and the like are assembled into a prefabricated whole, and the prefabricated whole is hung on a reactor shaft; then a pressure vessel is hung; accessories in the process of mounting are disassembled, and proper adjustment is carried out, wherein when the pressure vessel is arranged, the mounting work of a barrel insulating layer can be finished in one day, and compared with the time of nine days in a scheduled plan of the prior art, the mounting method saves eight days. In the mounting method, the hanging ring can avoid being operated with heavy load repeatedly for a long time, thereby reducing the probability of ring hanging accidents. The pressure vessel and the insulating layer also can avoid being hung in and out of the reactor shaft for many times, thereby reducing the probability of damage of the outer surface of the insulating layer.
Description
Technical field
The present invention relates to the installation of basic equipment in the nuclear power plant, relate to the installation method of insulating layer of nuclear reactor pressure vessel.
Background technology
At " reactor pressure vessel heat-insulation layer Equipment Specification " (Chinese Nuclear Power Design Academy, 2004-09-15 publishes) in regulation: " the cylindrical shell heat-insulation layer should be seated on the container support at pressure vessel; adjusts and vertically install from top to bottom with encircling to sling after qualified again, pressure vessel is returned after heat-insulation layer installs to sit in the support again ".
With Guangdong nuclear power group mountain range Australia nuclear power station the second stage of the project is example, and according to above-mentioned requirements, in the mountain range Australia nuclear power station the second stage of the project " nuclear island is installed three grades of plans ", the construction operation duration of " reactor building is introduced and be installed in to pressure vessel " is 27 working days.In the pressure vessel installation process, the installment work that also need intert heat-insulation layer, 9 working days of this work program duration.
The effect of insulating layer of nuclear reactor pressure vessel is to reduce the reactor thermal loss, and guarantees that the reactor ambient temperature can be not too high.Heat-insulation layer is set at the reactor pressure vessel outside, mainly comprises following components: closure head insulation layer, nozzle area heat-insulation layer, cylindrical shell heat-insulation layer and bottom (head) heat-insulation layer.Wherein, the each several part heat-insulation layer is mainly interconnected with rivet or bolt by some warming plates and forms.Warming plate is the critical piece that constitutes heat-insulation layer, its shell is the austenitic stainless steel thin plate that twin polishing becomes minute surface, and the compact arranged reflection horizon of several layers (the austenite stainless steel foil by 0.03～0.05mm thickness forms by certain colored type compacting usually) is housed in the shell.
In the installation process, what influence installation progress mainly is cylindrical shell heat-insulation layer 102, and as shown in Figure 1, all the other each several part heat-insulation layers are progressively installed after pressure vessel 101 is in place again.Emphasis of the present invention is that also the installation of cylindrical shell heat-insulation layer 102 improves.
In order more to clearly illustrate the structure of the heat-insulation layer of cylindrical shell shown in Fig. 1 102, its installation process of more convenient description can be launched whole cylindrical shell heat-insulation layer 102 as shown in Figure 2, is equivalent to tubular structure is expanded into planar structure.As can be seen, the cylindrical shell heat-insulation layer is divided into following components:
1) support ring P71/72 constitutes a circular steel structure, is used to support the weight of whole cylindrical shell heat-insulation layer; Wherein P71 and P72 are two kinds of arc steel constructions, and all are different for they and the physical dimension of pressure vessel nozzle contact site, so two kinds of numberings are arranged; For the ease of understanding, adopted the custom numbering of industry among the present invention; Wherein, if the parts of same names have different numberings, then represent the specification difference between them.
2) suspension bracket P75 comprises 6 vertical steel structures, support ring P71/72 and abutment ring P73/74 can be coupled together by them.
3) abutment ring P73/74 constitutes a circular steel structure, is installed in below the suspension bracket P75, is the upper limb of cylindrical shell heat-insulation layer.
4) cylindrical shell warming plate P1/9 is the main part of cylindrical shell heat-insulation layer, is made up of 8 top warming plate P9 and 64 all the other cylindrical shell warming plate P1.
5) bottom corner is the lower edge of cylindrical shell heat-insulation layer to warming plate P28/29.
6) flange periphery warming plate P77/78, these warming plates are installed in pressure vessel back in place, i.e. the figure topmost portion.
According to the regulation in " reactor pressure vessel heat-insulation layer Equipment Specification ", in the prior art, the cylindrical shell heat-insulation layer be the pressure vessel installation in position and adjust qualified after, from reactor shaft, pressure vessel 101 is sling again, install from top to down along the pressure vessel outer wall then.Basically install one section every day, when knocking off pressure vessel and the part heat-insulation layer that installed are fallen into reactor shaft, again pressure vessel is mentioned from reactor shaft after going into operation next day and continue to install next section heat-insulation layer.And so forth, need about 9 working days.Main construction procedure is:
1) pressure vessel falls into reactor shaft and is located on the support member (being referred to as the pressure vessel support ring traditionally) of pressure vessel;
2) support ring P71/72 is installed; Wherein, support ring P71/72 is a global concept, is the support of cylindrical shell heat-insulation layer, is different parts with pressure vessel support member in the previous step.
3) mention the about 500mm height of pressure vessel, suspension bracket P75 is installed;
4) abutment ring P73/74 is installed;
5) pressure vessel falls into reactor shaft and is located on the pressure vessel support member;
6) mention pressure vessel, the cylindrical shell warming plate P9 of topmost is installed;
7) pressure vessel falls into reactor shaft and is located on the pressure vessel support member;
8) mention pressure vessel, all the other cylindrical shell warming plate P1 are installed; According to this repeatedly, each section cylindrical shell warming plate P1 is installed;
9) mention pressure vessel, bottom corner is installed to warming plate P28/29, relief pressure vessel falls into reactor shaft and is located on the pressure vessel support member.
Wherein, total installation steps depend on that field condition, ring hang factors such as available, the workmen technical ability of (comprising that lifting commanding, ring hang the driver, pincers worker, survey crew etc. are installed), overtime, and ring herein hangs and is meant circular crane.Be not difficult to find that there is following problem in above-mentioned installation process:
1) installation of pressure container cylinder heat-insulation layer takies nuclear island that critical path time is installed is longer, according to 9 working days of common schedule needs, can influence pressure vessel completion date is installed.
2) ring that uses in the installation process hangs repeatedly heavy duty (256.6 tons of pressure vessel net weight) operation for a long time, and dangerous probability increases.
3) pressure vessel and heat-insulation layer thereof are repeatedly lifted up into from reactor shaft and are hung out, and have increased the probability that the heat-insulation layer outside surface is bruised.
Summary of the invention
Above-mentioned defective at prior art, the matter of utmost importance that the present invention will solve is the pressure container cylinder heat-insulation layer to be installed to install 27 required working days from pressure vessel 9 required working days remove, thereby whole nuclear island installation period is optimized, and guarantees that the installation of pressure container cylinder heat-insulation layer is safer, more reliable.
The technical solution adopted for the present invention to solve the technical problems is: a kind of installation method of insulating layer of nuclear reactor pressure vessel is provided, the cylindrical shell heat-insulation layer wherein is installed according to the following steps:
(1) utilize accessory that the abutment ring in the described cylindrical shell heat-insulation layer, suspension bracket, cylindrical shell warming plate are assembled into precast monolithic;
(2) described precast monolithic is lifted reactor shaft, and be put on the pressure vessel support member;
(3) pressure vessel that will install lifts described reactor shaft top, after pressure vessel falls and penetrates described precast monolithic one segment distance, the support ring of described cylindrical shell heat-insulation layer is installed in the ozzle top of pressure vessel;
(4) described support ring and suspension bracket are coupled together, adjust described pressure vessel in place again.
Among the present invention, described accessory can comprise channel-section steel circle, web joint and adjustable plate; Described adjustable plate is loaded on the outside of abutment ring and is used to regulate the diameter of abutment ring; Be connected for bolt between described abutment ring and the suspension bracket; Described web joint is welded on the outside of suspension bracket, and the lower surface of web joint is seated in the upper surface of channel-section steel circle.
Among the present invention, evenly be welded with at least three base plates in described channel-section steel circle bottom surface.Six described base plates are preferably arranged, and be located at 0 °, 60 °, 120 °, 180 °, 240 °, 300 ° positions of described channel-section steel circle bottom surface respectively.
In described step of the present invention (1), can earlier channel-section steel circle, web joint and adjustable plate in the accessory and abutment ring and the suspension bracket in the described heat-insulation layer be fitted together; Again their are lifted to a stand; Again top cylindrical shell warming plate is loaded on the abutment ring bottom, and then all the other cylindrical shell warming plates successively are installed, until assembling out described precast monolithic
In described step of the present invention (2), on described pressure vessel support member, place and a plurality of one to one lifting jack of described base plate earlier; The certain altitude of more described precast monolithic being sling, and remove described stand; Again described precast monolithic is lifted reactor shaft, and be put on the pressure vessel support member.
By technique scheme as can be seen, among the present invention, heat-insulation layer is assembled at the scene in advance, can not take the installation process of pressure vessel; When pressure vessel is installed, can finish the installment work of heat-insulation layer, compare with the 9 day time in the schedule of prior art and can save 8 day time, thereby the installation of pressure vessel is completed in advance with the time.In addition, among the present invention, can avoid ring to hang for a long time repeatedly heavy service, hang the probability that has an accident thereby can reduce ring; Also can avoid pressure vessel and heat-insulation layer thereof repeatedly to be lifted up into and hang out, thereby can reduce the probability that the heat-insulation layer outside surface is bruised from reactor shaft.
Description of drawings
The invention will be further described below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is the structure diagram of pressure vessel and heat-insulation layer thereof;
Fig. 2 is the stretch-out view of the cylindrical shell heat-insulation layer of pressure vessel;
Fig. 3 is the annexation enlarged drawing between P77/78 among Fig. 2, P75 and the P73;
Fig. 4 is the structural representation of the channel-section steel circle that uses in a preferred embodiment of the invention;
Fig. 5 is a structural representation between abutment ring in a preferred embodiment of the invention, suspension bracket, the channel-section steel circle;
Fig. 6 is the mounting structure synoptic diagram of a preferred embodiment of the invention middle cylinder body heat-insulation layer;
Fig. 7 is to be the enlarged diagram at center with the channel-section steel circle among Fig. 6.
Embodiment
One, the assembled on site of cylindrical shell heat-insulation layer
The improvement that the present invention relates to is the cylindrical shell heat-insulation layer, and field-installed main scope is other all parts except support ring P71/72 and flange periphery warming plate P77/78 in the cylindrical shell heat-insulation layer.
In the present embodiment, the external diameter of the pressure vessel 101 of next-door neighbour's cooling medium ozzle 103 belows is no more than Φ 4435mm.Because the gap between heat-insulation layer inwall and the pressure vessel outer wall is 18.5mm, so the internal diameter of abutment ring P73/74 is 4435+18.5+18.5=Φ 4472mm.
For circularity and the rigidity that keeps abutment ring P73/74, when specifically implementing, make a channel-section steel circle in advance.As shown in Figure 4, this channel-section steel circle 104 is formed by connecting by three sections circular arc steel, is connected by bolt between the three.The internal diameter of channel-section steel circle must also need be considered the height (such as interfering to avoid channel-section steel circle and bolt in the position corresponding with bolt perforate in advance) of the coupling bolt protrusion of abutment ring simultaneously greater than the external diameter Φ 4610mm of abutment ring P73/74.As can be seen from Figure 4, be welded with a base plate 105 respectively in 0 °, 60 °, 120 °, 180 °, 240 °, 300 ° positions of channel-section steel circle, this base plate is supported by lifting jack in the subsequent installation process.
As shown in Figure 5, wherein the diameter of abutment ring P73/74 is regulated by adjustable plate 107, because the internal diameter of channel-section steel circle is certain, so can regulate the diameter of abutment ring by the thickness that increases or reduce adjustable plate; After adjusting is finished, the adjustable plate point is welded on the channel-section steel circle.Be connected for bolt between abutment ring P73/74 and the suspension bracket P75; Channel-section steel circle 104 is whole supporting parts; The cross section of web joint 106 is a ladder structure of right angle, and its side end face is welded on the suspension bracket P75, and its lower surface is seated on the channel-section steel circle 104.
Assemble by Fig. 5, then abutment ring P73/74, suspension bracket P75 and the channel-section steel circle 104 that assembles lifted together to a stand, successively assemble cylindrical shell warming plate P1/9 again.Finally obtain the precast monolithic formed by abutment ring P73/74, suspension bracket P75, channel-section steel circle 104, cylindrical shell warming plate P1/9, web joint 106 and adjustable plate 107.The interim suspender that uses during lifting can be made of the steel I-beam that two length equate with channel-section steel circle external diameter.
The stand that uses in the assembling process then is in advance in the assembling zone that 20 meters platforms of reactor building delimited, and sets up on request with framing scaffold to form, and its effect is a support slot steel ring 104, and then supports whole precast monolithic.The requirement that stand is set up:
1) the stand overall height satisfies heat-insulation layer assembling needs, is 9m in the present embodiment;
2) stand should be annular, and internal diameter must be 5m in the present embodiment greater than the external diameter of heat-insulation layer;
3) stand can not influence heat-insulation layer assembling, particularly rivet junction.
During concrete assembling,, can realize by the rotary heat-insulating layer if when the local location of stand influence the rivet installation; In addition, the parts that directly contact with heat-insulation layer such as adjustable plate should use stainless steel material.
Two, the cylindrical shell heat-insulation layer is installed to pressure vessel
Above-mentioned assembled on site can obtain the precast monolithic of being made up of abutment ring P73/74, suspension bracket P75, channel-section steel circle 104, cylindrical shell warming plate P1/9, web joint 106 and adjustable plate 107.Then, as shown in Figure 6, place six lifting jack 108 on pressure vessel support member 109, the position of six base plates 105 is corresponding one by one on the position of lifting jack and the channel-section steel circle, then each lifting jack is adjusted to identical absolute altitude.
Hang the aforementioned precast monolithic certain altitude of slinging by interim suspender and ring, remove described stand then, again precast monolithic is lifted reactor shaft, and be put on the lifting jack 108 on the pressure vessel support member 109, wherein, the lower surface of base plate 105 is just in time aimed on the top of each lifting jack.During concrete enforcement, the quantity of base plate and lifting jack can be carried out suitable adjustment, for example is all three, or is all eight.
Remove interim suspender then, assemble the pressure vessel suspender again, and pressure vessel is directly lifted the reactor shaft top.
After pressure vessel falls and penetrates heat-insulation layer one segment distance, the support ring P71/72 of heat-insulation layer is installed in pressure vessel is responsible for the mouth top.
Regulate cylindrical shell heat-insulation layer (for example regulating) then, again support ring P71/72 and suspension bracket P75 are coupled together by the distance of regulating abutment ring P73/74 and pressure vessel outer wall.
Remove lifting jack 108, channel-section steel circle 104, web joint 106 and adjustable plate 107 these accessories.
With the pressure vessel installation in position, be positioned on the pressure vessel support member 109 at last, and adjust to the optimum position.
As can be seen from the above-described embodiment, wherein earlier abutment ring P73/74, suspension bracket P75, channel-section steel circle 104, cylindrical shell warming plate P1/9 etc. are assembled into precast monolithic, and this precast monolithic lifted reactor shaft, and then the lifting pressure vessel, remove the accessory in the installation process at last and carry out suitable adjustment; As seen, the cylindrical shell heat-insulation layer is assembled at the scene in advance, can not take the installation process of pressure vessel, when pressure vessel is installed, can finish the installment work of cylindrical shell heat-insulation layer with the time, compare with the 9 day time in the schedule of prior art and can save 8 day time, thereby the installation of pressure vessel is completed in advance.
In addition, in the foregoing description, can avoid ring to hang for a long time repeatedly heavy service, hang the probability that has an accident thereby can reduce ring; Also can avoid pressure vessel and heat-insulation layer thereof repeatedly to be lifted up into and hang out, thereby can reduce the probability that the heat-insulation layer outside surface is bruised from reactor shaft.
Claims (8)
1, a kind of installation method of insulating layer of nuclear reactor pressure vessel is characterized in that, the cylindrical shell heat-insulation layer is installed according to the following steps:
(1) utilize accessory that the abutment ring (P73/74) in the described cylindrical shell heat-insulation layer, suspension bracket (P75), cylindrical shell warming plate (P1/9) are assembled into precast monolithic;
(2) described precast monolithic is lifted reactor shaft, and be put on the pressure vessel support member (109);
(3) pressure vessel that will install (101) lifts described reactor shaft top, after pressure vessel falls and penetrates described precast monolithic one segment distance, the support ring (P71/72) of described cylindrical shell heat-insulation layer is installed in ozzle (103) top of pressure vessel;
(4) described support ring (P71/72) and suspension bracket (P75) are coupled together, adjust described pressure vessel (101) in place again.
2, method according to claim 1 is characterized in that, described accessory comprises channel-section steel circle (104), web joint (106) and adjustable plate (107);
Described adjustable plate (107) is loaded on the outside of abutment ring (P73/74) and is used to regulate the diameter of abutment ring (P73/74);
Be connected for bolt between described abutment ring (P73/74) and the suspension bracket (P75);
Described web joint (106) is welded on the outside of suspension bracket (P75), and the lower surface of web joint (106) is seated in the upper surface of channel-section steel circle (104).
3, method according to claim 2 is characterized in that, evenly is welded with at least three base plates (105) in described channel-section steel circle (104) bottom surface.
4, method according to claim 3 is characterized in that, wherein has six described base plates (104), and is located at 0 °, 60 °, 120 °, 180 °, 240 °, 300 ° positions of described channel-section steel circle (104) bottom surface respectively.
5, method according to claim 4, it is characterized in that, in described step (1), earlier abutment ring (P73/74) and suspension bracket (P75) in the channel-section steel circle (104) in the accessory, web joint (106) and adjustable plate (107) and the described heat-insulation layer are fitted together; Again their are lifted to a stand; Again top cylindrical shell warming plate (P9) is loaded on abutment ring (P73/74) bottom, and then all the other cylindrical shell warming plates (P1) successively are installed, until assembling out described precast monolithic
6, according to each described method among the claim 3-5, it is characterized in that, in described step (2), go up at described pressure vessel support member (109) earlier and place and a plurality of one to one lifting jack of described base plate (103) (108); The certain altitude of more described precast monolithic being sling, and remove described stand; Again described precast monolithic is lifted reactor shaft, and be put on the pressure vessel support member (109).
7, method according to claim 6, it is characterized in that, in described step (4), after described support ring (P71/72) and suspension bracket (P75) coupled together, remove the accessory of described lifting jack (108), channel-section steel circle (104), web joint (106) and adjustable plate (107) earlier, adjust described pressure vessel (101) in place again.
8, method according to claim 7 is characterized in that, described pressure vessel installation in position is on described pressure vessel support member (109).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2008100671068A CN101577145B (en) | 2008-05-07 | 2008-05-07 | Mounting method for insulating layer of nuclear reactor pressure vessel |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2008100671068A CN101577145B (en) | 2008-05-07 | 2008-05-07 | Mounting method for insulating layer of nuclear reactor pressure vessel |
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| CN101577145A true CN101577145A (en) | 2009-11-11 |
| CN101577145B CN101577145B (en) | 2011-08-17 |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102061788A (en) * | 2010-11-09 | 2011-05-18 | 中国核工业华兴建设有限公司 | Method for mounting bottom plates and cylinder of steel lining of nuclear power plant |
| CN102522126A (en) * | 2011-12-30 | 2012-06-27 | 中国核工业第五建设有限公司 | Mounting process for metal reflective heat-insulation layers of pressure vessel of nuclear island |
| CN107958711A (en) * | 2017-12-18 | 2018-04-24 | 中广核研究院有限公司 | A kind of reactor pit and reactor pit system |
| CN109243626A (en) * | 2018-08-17 | 2019-01-18 | 中国核工业二三建设有限公司 | ACP1000 nuclear pressure container cylinder insulating layer installation method |
| CN109723938A (en) * | 2019-01-31 | 2019-05-07 | 中国核工业二三建设有限公司 | ACPR1000 reactor pressure vessel heap chamber heat-insulation support installation method |
| CN113944826A (en) * | 2021-10-22 | 2022-01-18 | 中国原子能科学研究院 | Thermal insulation assembly of reactor vessel |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5268944A (en) * | 1992-06-24 | 1993-12-07 | Westinghouse Electric Corp. | Nuclear reactor having a polyhedral primary shield and removable vessel insulation |
| US5699394A (en) * | 1995-07-13 | 1997-12-16 | Westinghouse Electric Corporation | Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel |
| CN1111872C (en) * | 1996-12-30 | 2003-06-18 | 常州飞机制造厂 | Metal insulating layer of nuclear reactor pressure vessel and pipeline |
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2008
- 2008-05-07 CN CN2008100671068A patent/CN101577145B/en active Active
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102061788A (en) * | 2010-11-09 | 2011-05-18 | 中国核工业华兴建设有限公司 | Method for mounting bottom plates and cylinder of steel lining of nuclear power plant |
| CN102061788B (en) * | 2010-11-09 | 2012-11-21 | 中国核工业华兴建设有限公司 | Method for mounting bottom plates and cylinder of steel lining of nuclear power plant |
| CN102522126A (en) * | 2011-12-30 | 2012-06-27 | 中国核工业第五建设有限公司 | Mounting process for metal reflective heat-insulation layers of pressure vessel of nuclear island |
| CN102522126B (en) * | 2011-12-30 | 2014-04-16 | 中国核工业第五建设有限公司 | Mounting process for metal reflective heat-insulation layers of pressure vessel of nuclear island |
| CN107958711A (en) * | 2017-12-18 | 2018-04-24 | 中广核研究院有限公司 | A kind of reactor pit and reactor pit system |
| CN109243626A (en) * | 2018-08-17 | 2019-01-18 | 中国核工业二三建设有限公司 | ACP1000 nuclear pressure container cylinder insulating layer installation method |
| CN109243626B (en) * | 2018-08-17 | 2020-10-23 | 中国核工业二三建设有限公司 | ACP1000 nuclear power pressure vessel cylinder heat-insulating layer installation method |
| CN109723938A (en) * | 2019-01-31 | 2019-05-07 | 中国核工业二三建设有限公司 | ACPR1000 reactor pressure vessel heap chamber heat-insulation support installation method |
| CN113944826A (en) * | 2021-10-22 | 2022-01-18 | 中国原子能科学研究院 | Thermal insulation assembly of reactor vessel |
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|---|---|
| CN101577145B (en) | 2011-08-17 |
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Effective date of registration: 20170329 Address after: Futian District Shenzhen City, Guangdong province 518023 Shennan Road No. 69 Patentee after: China Nuclear Power Engineering Co., Ltd. Patentee after: Hualong International Nuclear Power Technology Co., Ltd. Address before: Futian District Shenzhen City, Guangdong province 518023 Shennan Road No. 69 Patentee before: China Nuclear Power Engineering Co., Ltd. |
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