CN203325479U - Pressurized water reactor pressure vessel - Google Patents
Pressurized water reactor pressure vessel Download PDFInfo
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- CN203325479U CN203325479U CN2013204177834U CN201320417783U CN203325479U CN 203325479 U CN203325479 U CN 203325479U CN 2013204177834 U CN2013204177834 U CN 2013204177834U CN 201320417783 U CN201320417783 U CN 201320417783U CN 203325479 U CN203325479 U CN 203325479U
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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 utility model discloses a pressurized water reactor pressure vessel. The pressurized water reactor pressure vessel comprises a top cover, an upper-portion vessel assembly, a reactor core barrel body (6) and a lower-portion vessel assembly. The upper-portion vessel assembly and the lower-portion vessel assembly are welded to the upper end and the lower end of the reactor core barrel body (6) respectively to form space used for accommodating a fuel assembly; the top cover is connected with the upper-portion assembly. The pressurized water reactor pressure vessel is characterized in that the reactor core barrel body (6) is of an integrated structure; because welding seams are omitted, the pressurized water reactor pressure vessel has the advantages of solving the problem that under the high-strength irradiation condition, the reactor core barrel body leaks easily and reducing detection and maintenance workloads in service.
Description
Technical field
The utility model relates to the nuclear industry field, is specifically related to a kind of presurized water reactor reactor pressure vessel.
Background technology
The presurized water reactor reactor pressure vessel is one of key equipment of PWR nuclear power plant, its Main Function comprise following some:
1. the reactor core parts, in-pile component and the In-core Instrumentation parts that hold reactor;
2. support reactor control rod driving mechanism and other heap roof construction parts;
3. the pressure boundary of anabolic reaction reactor coolant system;
4. construct the important barrier of second of nuclear island reactor core radiological health.
The presurized water reactor reactor pressure vessel is non-exchange within the phase in longevity, thereby the reliability of presurized water reactor reactor pressure vessel is the key factor that determines the PWR nuclear power plant life-span.Along with the development of nuclear industry, the economy that the improves nuclear power plant development trend that is inevitable, so the enhancing of reactor pressure vessel life-time dilatation and reliability is to guarantee the long-lived phase operation of nuclear power plant, improves the key of economy.
At present, moving and be generally 40 years in the designed life of the presurized water reactor reactor pressure vessel of building, all there are certain defect in its material, structure and manufacture.For example the impurity element of container body material and radiation sensitive constituent content are higher, there is girth joint on strong irradiated site reactor core cylinder section mother metal, fast neutron fluence in the full phase in longevity is higher, and the penetration piece on the bottom container assembly exists and destroys and cause the possibility of Core uncovering.Along with the operation of reactor, the fast neutron fluence that the presurized water reactor reactor pressure vessel bears is constantly accumulated, and above defect all can become the weak link of pressure vessel, thereby has reduced the serviceable life of pressure vessel.
As shown in Figure 1, the structure of existing presurized water reactor reactor pressure vessel is as follows:
Mainly comprise top cover A12, upper container assembly A19, reactor core cylindrical shell A13, cradle cylinder body A14 and bottom container assembly A15, fuel assembly 17 is set in cradle cylinder body A14, wherein the attachment weld A18 of upper container assembly A19 and reactor core cylindrical shell A13 is positioned at the axial range of fuel assembly 17, and the attachment weld A18 of bottom container assembly A15 and reactor core cylindrical shell A13 also is positioned at the axial range of fuel assembly 17.Simultaneously, reactor core cylindrical shell A13 is welded by upper and lower two parts.Article 3, attachment weld A18 is positioned at the axial range of fuel assembly 17.Irradiation intensity in the axial range of fuel assembly 17 is large, and the end of term in the longevity peak value of position while welding accumulative total fast neutron fluence is very high, and the irradiation tolerance of weld seam a little less than, the radiation embrittlement of weld metal has restricted the serviceable life of reactor pressure vessel.
In addition, also comprise the penetration piece A16 be arranged on bottom container assembly A15, penetration piece A16 and bottom container assembly A15 are welded to connect, for to reactor core inside, sending into pick-up unit, to carry out the neutron flux detection.Between penetration piece A16 and bottom container assembly A15, adopt the fillet weld of local through welding to be connected, under accident conditions, can become the pressure vessel weak link, have leakage and cause the risk of coolant loss.
The utility model content
The purpose of this utility model is to overcome the weld seam on the reactor core cylindrical shell in existing presurized water reactor reactor pressure vessel and is subject to irradiation easily to cause radiation embrittlement, shortens the problem in pressure vessel life-span, and a kind of presurized water reactor reactor pressure vessel is provided.
The purpose of this utility model is achieved through the following technical solutions:
A kind of presurized water reactor reactor pressure vessel, comprise top cover, upper container assembly, reactor core cylindrical shell and bottom container assembly, upper container assembly, bottom container assembly weld with the top and bottom of reactor core cylindrical shell the space that is configured for holding fuel assembly respectively, top cover is connected with the upper container assembly, and described reactor core cylindrical shell is monolithic construction.
Description from background technology can find out, in traditional pressure vessel, the reactor core cylindrical shell is welded to form by upper and lower two parts.Connect the axial range that upper and lower two-part weld seam is positioned at fuel assembly, irradiation intensity is large, easily causes the radiation embrittlement of weld metal.In addition, connecting the center of close fuel assembly of upper and lower two-part weld seam, will be subject to the irradiation of maximum dose, solve the problem that this position while welding easily produces radiation embrittlement, is the key that improves presurized water reactor reactor pressure vessel life-span and security.
The inventor after deliberation, adopt the reactor core cylindrical shell of monolithic construction, that is to say the weld seam of having cancelled on the reactor core cylindrical shell, thereby solved the reactor core cylindrical shell under the high intensity radiation condition, the problem of leaking easily occurs, the life-span and the security that have effectively improved the presurized water reactor reactor pressure vessel.Reduced when in-service simultaneously and checked and the workload of maintenance.
As the first prioritization scheme of the present utility model, the bottom of described reactor core cylindrical shell extends to described fuel assembly below, and the top of described reactor core cylindrical shell extends to described fuel assembly top.
Said structure makes the weld seam between reactor core cylindrical shell and upper container assembly, weld seam between reactor core cylindrical shell and bottom container assembly is away from the axial range of fuel assembly, that is to say the weld seam zone large away from irradiation intensity that makes the irradiation tolerance weak, greatly reduce the impact of irradiation butt welded seam, further improved life-span and the security of presurized water reactor reactor pressure vessel.
As the second prioritization scheme of the present utility model, the internal diameter of described reactor core cylindrical shell is 4340mm.
The internal diameter of existing reactor core cylindrical shell is 3989mm, reaching under the requirement that both fuel assemblies of determined number is installed, distance between the inside surface of the outside surface of cradle cylinder body and reactor core cylindrical shell is less, causes the water gap between the inside surface of the outside surface of cradle cylinder body and reactor core cylindrical shell thinner.In reactor, chilled water is taken away the heat of reactor fuel element surface on the one hand, a large amount of neutrons that slowing down absorption are revealed from reactor core on the other hand.Than thin water gap, cause the neutron injection rate IR of reactor core cylindrical shell large, affect the life-span of presurized water reactor reactor pressure vessel.
This prioritization scheme has increased the internal diameter of reactor core cylindrical shell, make the thickness of water gap be increased to 295mm simultaneously, with respect to the water gap of 245.1mm in existing pressure vessel, improved the neutron-absorbing amount of chilled water, can effectively improve the life-span of presurized water reactor reactor pressure vessel.
In addition, the internal diameter of reactor core cylindrical shell is set as to 4340mm, considers on the one hand the thickness that increases the water gap, consider on the other hand the difficulty of processing of reactor core cylindrical shell.
Distance between the inside surface of the outside surface of described cradle cylinder body and described reactor core cylindrical shell is 295mm.The increase of equilibrium water gap thickness to the full extent of above-mentioned size and the difficulty of processing of reactor core cylindrical shell are obtained best performance in cost acceptable situation.
As the third prioritization scheme of the present utility model, also comprise penetration piece, penetration piece is arranged at the top of described top cover.This prioritization scheme is that penetration piece of the prior art is transferred to the top cover top from the bottom container assembly, has eliminated the risk that causes coolant loss because of the generation of the weld seam between penetration piece and bottom container assembly leakage.
As the 4th kind of prioritization scheme of the present utility model, described top cover comprises upper cover and top cover flange, and upper cover is connected with the top cover flange; Described upper container assembly comprises linkage section and adapter, and the top cover flange is connected with linkage section, and linkage section is connected with the upper end of described reactor core cylindrical shell, takes over and is arranged on linkage section; Described bottom container assembly comprises transition section and low head, and low head is connected with transition section, and transition section is connected with the lower end of described reactor core cylindrical shell.
As the 5th kind of prioritization scheme of the present utility model, described top cover, upper container assembly, reactor core cylindrical shell and bottom container assembly consist of 16MND5 low alloy steel.16MND5 low alloy steel is a kind of metal material of record in French presurized water reactor nuclear islands equipment design-build rule (RCC-M), and radiation sensitive element wherein (phosphorus, sulphur, copper, nickel etc.) content is lower, is applicable to the occasion that irradiation intensity is higher.Adopt 16MND5 low alloy steel to manufacture top cover, upper container assembly, reactor core cylindrical shell and bottom container assembly, can effectively improve serviceable life of the present utility model and security.
As the 6th kind of prioritization scheme of the present utility model, also comprise irradiation monitoring pipe, irradiation monitoring pipe is arranged in described reactor core cylindrical shell, and the supervision sample that 16MND5 low alloy steel forms is housed in irradiation monitoring pipe.In the reactor operation process, the presurized water reactor reactor pressure vessel that need to watch with the deepest concern is subject to the performance change after irradiation.Adopt the material identical with the presurized water reactor reactor pressure vessel to form irradiation monitoring pipe, regularly irradiation monitoring pipe is checked, can learn the performance change of presurized water reactor reactor pressure vessel, the security that guarantees the presurized water reactor reactor pressure vessel is had to very important effect.
Further, the quantity of described irradiation monitoring pipe is 4 ~ 6.
In sum, advantage of the present utility model and beneficial effect are:
1. adopt monoblock type reactor core cylindrical shell, cancelled the weld seam on the reactor core cylindrical shell, solved the reactor core cylindrical shell under the high intensity radiation condition, the problem of radiation embrittlement easily occurs in weld metal, has reduced when in-service simultaneously and has checked and the workload of maintenance;
2. the bottom of reactor core cylindrical shell is positioned at the cradle cylinder body below, the top of reactor core cylindrical shell is positioned at the top of fuel assembly, make the weak weld seam zone large away from irradiation intensity of irradiation tolerance, greatly reduce the impact of irradiation butt welded seam, further improved life-span and the security of presurized water reactor reactor pressure vessel;
3. increase internal diameter and the water gap thickness of reactor core cylindrical shell, improved the neutron-absorbing amount of chilled water, the life-span of effectively having improved the presurized water reactor reactor pressure vessel;
4. penetration piece is arranged to the top of described top cover, has eliminated the risk that causes cooling medium to overflow because of the generation of the weld seam between penetration piece and bottom container assembly leakage;
5. adopt 16MND5 low alloy steel to manufacture top cover, upper container assembly, reactor core cylindrical shell and bottom container assembly, effectively improved serviceable life of the present utility model and security;
6. irradiation monitoring pipe is set, the performance change of presurized water reactor reactor pressure vessel is exercised supervision, can guarantee the security of presurized water reactor reactor pressure vessel.
The accompanying drawing explanation
In order to be illustrated more clearly in embodiment of the present utility model, below will be briefly described describing the required accompanying drawing of using in the utility model embodiment.Apparent, the accompanying drawing in the following describes is only some embodiment that put down in writing in the utility model, to those skilled in the art, in the situation that do not pay creative work, can also, according to following accompanying drawing, obtain other accompanying drawing.
The structural representation that Fig. 1 is traditional presurized water reactor reactor pressure vessel;
Fig. 2 is structural representation of the present utility model;
Wherein, the parts title that Reference numeral is corresponding is as follows:
The 1-upper cover, 2-top cover flange, the 3-linkage section, 4-takes over, the 5-weld seam, 6-reactor core cylindrical shell, 7-irradiation monitoring pipe, the 8-cradle cylinder body, 9-transition section, 10-low head, the 11-penetration piece, 12-top cover A, 13-reactor core cylindrical shell A, 14-cradle cylinder body A, 15-bottom container assembly A, 16-penetration piece A, the 17-fuel assembly, 18-weld seam A, 19-upper container assembly A.
Embodiment
In order to make those skilled in the art understand better the utility model, below in conjunction with the accompanying drawing in the utility model embodiment, the technical scheme in the utility model embodiment is carried out to clear, complete description.Apparent, embodiment described below is only the part in the utility model embodiment, rather than all.Embodiment based on the utility model record, those skilled in the art are not in the situation that pay other all embodiment that creative work obtains, in the scope of all protecting at the utility model.
Embodiment 1:
As shown in Figure 2, a kind of presurized water reactor reactor pressure vessel, comprise top cover, upper container assembly, reactor core cylindrical shell 6 and bottom container assembly, upper container assembly, bottom container assembly weld with the top and bottom of reactor core cylindrical shell 6 space that is configured for holding fuel assembly respectively, top cover is connected with the upper container assembly, and described reactor core cylindrical shell 6 is monolithic construction.
The present embodiment is to provide a kind of presurized water reactor reactor pressure vessel that adopts the reactor core cylindrical shell 6 of monolithic construction, makes the weld seam do not existed in the axial range of fuel assembly a little less than the irradiation tolerance, improves security and the life-span of the present embodiment.
The structure of the present embodiment can make the peak reduction of position while welding place accumulative total fast neutron fluence original on the end of term in longevity reactor core cylindrical shell 6 more than 90%.
It should be noted that, in the foregoing description, fuel assembly is only used for illustrating effect of the present utility model, and protection domain of the present utility model is not limited to the combination of presurized water reactor reactor pressure vessel and fuel assembly.When reading the application, protection domain of the present utility model can not be contracted to the combination of presurized water reactor reactor pressure vessel and fuel assembly.
In use, hanging basket assembly 8 is arranged at the utility model inside to the utility model, for the fixed fuel assembly.
Embodiment 2:
As shown in Figure 2, the present embodiment is on the basis of above-described embodiment, and the bottom of described reactor core cylindrical shell 6 extends to described fuel assembly below, and the top of described reactor core cylindrical shell 6 extends to described fuel assembly top.Can find out, this structure makes the zone that weld seam 5 is large away from irradiation intensity, has greatly reduced the impact of the irradiation butt welded seam 5 of fuel assembly generation, the life-span and the security that have further improved the presurized water reactor reactor pressure vessel.
Embodiment 3:
As shown in Figure 2, the present embodiment is on the basis of above-mentioned any one embodiment, and preferably the internal diameter of reactor core cylindrical shell 6 is 4340mm.Space between the inside surface of the outside surface of cradle cylinder body 8 and reactor core cylindrical shell 6 is the water gap.When the present embodiment is worked, chilled water can be filled the full water gap, and the increase of water gap thickness has improved the neutron-absorbing amount of chilled water, the life-span that can effectively improve the presurized water reactor reactor pressure vessel.In the present embodiment, the thickness of water gap is 295mm.
Embodiment 4:
As shown in Figure 2, the present embodiment, on the basis of above-mentioned any one embodiment, also comprises penetration piece 11, and penetration piece 11 is arranged at the top of described top cover.When work, pick-up unit stretches into reactor core inside by penetration piece 11 from the top cover top and carries out the neutron flux detection.
The mode that the present embodiment is welded to connect with respect to penetration piece A16 in traditional pressure vessel as shown in Figure 1 and bottom container assembly A15, eliminated and the risk that causes cooling medium to overflow occurred to leak because of the weld seam between penetration piece and low head.
Embodiment 5:
As shown in Figure 2, the present embodiment is on the basis of above-mentioned any one embodiment, and described top cover comprises upper cover 1 and top cover flange 2, and upper cover 1 is connected with top cover flange 2; Described upper container assembly comprises linkage section 3 and adapter 4, and top cover flange 2 is connected with linkage section 3, and linkage section 3 is connected with the upper end of described reactor core cylindrical shell 6, takes over 4 and is arranged at linkage section) on; Described bottom container assembly comprises transition section 9 and low head 10, and low head 10 is connected with transition section 9, and transition section 9 is connected with the lower end of described reactor core cylindrical shell 6.Take over 4 for realizing the turnover of chilled water.
Embodiment 6:
As shown in Figure 2, the present embodiment is on the basis of above-mentioned any one embodiment, and described top cover, upper container assembly, reactor core cylindrical shell 6 and bottom container assembly consist of 16MND5 low alloy steel.
Embodiment 7:
As shown in Figure 2, the present embodiment, on the basis of embodiment 6, also comprises irradiation monitoring pipe 7, and irradiation monitoring pipe 7 is arranged in described reactor core cylindrical shell 6, and the supervision sample that 16MND5 low alloy steel forms is housed in irradiation monitoring pipe 7.When the present embodiment is worked, need regularly to take out irradiation monitoring pipe 7, to detect the performance of irradiation monitoring pipe 7, thereby learn the performance change of presurized water reactor reactor pressure vessel, guarantee the safe operation of the present embodiment.
Usually, in use, irradiation monitoring pipe 7 is arranged on hanging basket assembly 8.
Embodiment 8:
The present embodiment is on the basis of embodiment 7, and the quantity of described irradiation monitoring pipe 7 is 4 ~ 6.
Embodiment 9:
The present embodiment, on the basis of embodiment 8, also arranges 2 ~ 6 standby supervision pipes.In the end an irradiation monitoring pipe 7 is extracted out rear until long-time interior (20 ~ 30 years) in the end of term in longevity will face the situation that there is no irradiation monitoring pipe supervision in heap, if the reactor operation appearance is abnormal, has just lacked the means of evaluation.Therefore, 2 ~ 6 standby supervision pipes are set, prepare for the supervision in operation later stage, also can be used for follow-up evaluation of further lengthening the life.
Those skilled in the art will appreciate that, can further selectively apply many variations and the structure that above a plurality of exemplary embodiments are described and form other possible embodiment of the present utility model.Consider those skilled in the art's ability, this paper do not provide in detail or describe the content that likely repeats, but all combinations of otherwise comprising and may embodiment the part that is the application.
Claims (8)
1. a presurized water reactor reactor pressure vessel, comprise top cover, upper container assembly, reactor core cylindrical shell (6) and bottom container assembly, upper container assembly, bottom container assembly weld with the top and bottom of reactor core cylindrical shell (6) space that is configured for holding fuel assembly respectively, top cover is connected with the upper container assembly, it is characterized in that: described reactor core cylindrical shell (6) is monolithic construction.
2. a kind of presurized water reactor reactor pressure vessel according to claim 1 is characterized in that: the bottom of described reactor core cylindrical shell (6) extends to described fuel assembly below, and the top of described reactor core cylindrical shell (6) extends to described fuel assembly top.
3. a kind of presurized water reactor reactor pressure vessel according to claim 1, it is characterized in that: the internal diameter of described reactor core cylindrical shell (6) is 4340mm.
4. a kind of presurized water reactor reactor pressure vessel according to claim 1, it is characterized in that: also comprise penetration piece (11), penetration piece (11) is arranged at the top of described top cover.
5. a kind of presurized water reactor reactor pressure vessel according to claim 1, it is characterized in that: described top cover comprises upper cover (1) and top cover flange (2), upper cover (1) is connected with top cover flange (2);
Described upper container assembly comprises linkage section (3) and adapter (4), and top cover flange (2) is connected with linkage section (3), and linkage section (3) is connected with the upper end of described reactor core cylindrical shell (6), takes over (4) and is arranged on linkage section (3);
Described bottom container assembly comprises transition section (9) and low head (10), and low head (10) is connected with transition section (9), and transition section (9) is connected with the lower end of described reactor core cylindrical shell (6).
6. according to the described a kind of presurized water reactor reactor pressure vessel of claim 1 ~ 5 any one, it is characterized in that: described top cover, upper container assembly, reactor core cylindrical shell (6) and bottom container assembly consist of 16MND5 low alloy steel.
7. a kind of presurized water reactor reactor pressure vessel according to claim 6, it is characterized in that: also comprise irradiation monitoring pipe (7), irradiation monitoring pipe (7) is arranged in described reactor core cylindrical shell (6), and the supervision sample that 16MND5 low alloy steel forms is housed in irradiation monitoring pipe (7).
8. a kind of presurized water reactor reactor pressure vessel according to claim 7, it is characterized in that: the quantity of described irradiation monitoring pipe (7) is 4 ~ 6.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013204177834U CN203325479U (en) | 2013-07-15 | 2013-07-15 | Pressurized water reactor pressure vessel |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013204177834U CN203325479U (en) | 2013-07-15 | 2013-07-15 | Pressurized water reactor pressure vessel |
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| CN203325479U true CN203325479U (en) | 2013-12-04 |
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| CN2013204177834U Expired - Lifetime CN203325479U (en) | 2013-07-15 | 2013-07-15 | Pressurized water reactor pressure vessel |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105244063A (en) * | 2015-09-08 | 2016-01-13 | 中国核动力研究设计院 | Solid reactor irradiation structure for pressurized water reactor |
| CN105788664A (en) * | 2016-05-06 | 2016-07-20 | 中国核动力研究设计院 | Pressurized-water nuclear reactor structure |
| CN106710648A (en) * | 2016-12-16 | 2017-05-24 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel irradiation damage monitoring method |
| CN107731319A (en) * | 2017-10-16 | 2018-02-23 | 中国核动力研究设计院 | A kind of Integral forming type core shroud structure for presurized water reactor |
| CN108206061A (en) * | 2017-12-01 | 2018-06-26 | 肇庆鼎湖檀树电子科技有限公司 | Nuclear power power generator |
| CN111916232A (en) * | 2020-08-13 | 2020-11-10 | 中国核动力研究设计院 | Light water nuclear reactor structure |
| CN112071450A (en) * | 2020-08-05 | 2020-12-11 | 中国原子能科学研究院 | External pressure type reactor pressure vessel |
-
2013
- 2013-07-15 CN CN2013204177834U patent/CN203325479U/en not_active Expired - Lifetime
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105244063A (en) * | 2015-09-08 | 2016-01-13 | 中国核动力研究设计院 | Solid reactor irradiation structure for pressurized water reactor |
| CN105244063B (en) * | 2015-09-08 | 2017-08-01 | 中国核动力研究设计院 | A kind of real heap for presurized water reactor irradiates structure |
| CN105788664A (en) * | 2016-05-06 | 2016-07-20 | 中国核动力研究设计院 | Pressurized-water nuclear reactor structure |
| CN106710648A (en) * | 2016-12-16 | 2017-05-24 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel irradiation damage monitoring method |
| CN106710648B (en) * | 2016-12-16 | 2018-03-06 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel irradiation damage monitoring method |
| CN107731319A (en) * | 2017-10-16 | 2018-02-23 | 中国核动力研究设计院 | A kind of Integral forming type core shroud structure for presurized water reactor |
| CN108206061A (en) * | 2017-12-01 | 2018-06-26 | 肇庆鼎湖檀树电子科技有限公司 | Nuclear power power generator |
| CN112071450A (en) * | 2020-08-05 | 2020-12-11 | 中国原子能科学研究院 | External pressure type reactor pressure vessel |
| CN112071450B (en) * | 2020-08-05 | 2023-08-18 | 中国原子能科学研究院 | External pressure type reactor pressure vessel |
| CN111916232A (en) * | 2020-08-13 | 2020-11-10 | 中国核动力研究设计院 | Light water nuclear reactor structure |
| CN111916232B (en) * | 2020-08-13 | 2022-03-01 | 中国核动力研究设计院 | Light water nuclear reactor structure |
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