GB2541475B - Structural layout of primary loop of nuclear reactor coolant system - Google Patents
Structural layout of primary loop of nuclear reactor coolant system Download PDFInfo
- Publication number
- GB2541475B GB2541475B GB1521984.3A GB201521984A GB2541475B GB 2541475 B GB2541475 B GB 2541475B GB 201521984 A GB201521984 A GB 201521984A GB 2541475 B GB2541475 B GB 2541475B
- Authority
- GB
- United Kingdom
- Prior art keywords
- primary
- primary loop
- nuclear reactor
- coolant system
- pressure vessel
- 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.)
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- 239000002826 coolant Substances 0.000 title claims description 77
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 10
- 125000002619 bicyclic group Chemical group 0.000 claims description 4
- 239000003758 nuclear fuel Substances 0.000 description 21
- 230000001133 acceleration Effects 0.000 description 10
- 238000005516 engineering process Methods 0.000 description 8
- 230000004048 modification Effects 0.000 description 5
- 238000012986 modification Methods 0.000 description 5
- 239000000446 fuel Substances 0.000 description 3
- 206010016275 Fear Diseases 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 125000002950 monocyclic group Chemical group 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 238000010206 sensitivity analysis Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/04—Means for suppressing fires ; Earthquake protection
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/084—Boiling water reactors
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
SPECIFICATION
Structural Layout of Primary Loop of Nuclear Reactor Coolant System FIELD OF THE INVENTION
[0001] The present invention generally relates to nuclear power plants and, more particularly, to a structural layout of primary loop of nuclear reactor coolant system.
BACKGROUND OF THE INVENTION
[0002] With the requirements of economic development and environment protection, as one kind of new clean energy technologies, nuclear power technology developed rapidly in recent years. During the nuclear plant design, more and more attention has been paid to the safety performances of the nuclear power.
[0003] In the prior art, the primary loop of nuclear reactor coolant system is arranged in a reactor building, wherein the pressure vessel is located in the center of the reactor building. Three steam generators and three primary coolant pumps are set around the pressure vessel, and an angle between each group consisting of one steam generator and one primary coolant pump is 120 degrees. A pressurizer is assembled to a hot leg of the primary coolant pipe.
[0004] Referring to Fig. 1, in the conventional primary loop of nuclear reactor coolant system, the attitude difference L’ between a center of the primary coolant pipe 12’ connected to the pressure vessel 10’ and an upper surface 14’ of the raft base plate in the reactor building is about 12.4 meters.
[0005] However, the seismic acceleration of the conventional primary loop of nuclear reactor coolant system is designed according to 0.2g. Correspondingly, the seismic capacity of the reactor fuel assembly is designed according to 0.2g. The conventional primary loop of nuclear reactor coolant system has the following disadvantages: 1) the seismic acceleration of the reactor is designed according to 0.2g, which will lead to narrower range of target site selection of the nuclear power plant and smaller seismic margin; 2) the safety performance of the conventional primary loop of nuclear reactor coolant system is not higher enough to respond to disasters, such as earthquake; 3) the requirements of the seismic structural design of the reactor fuel assembly is too strict and complex; and 4) the conventional primary loop of nuclear reactor coolant system cannot meet the requirements of internationally recognized third generation of nuclear power technology.
[0006] What is needed, therefore, is to provide a structural layout of primary loop of nuclear reactor coolant system which has higher seismic capacity.
SUMMARY OF THE INVENTION
[0007] One object of the present invention is to provide a structural layout of primary loop of nuclear reactor coolant system which has higher seismic capacity.
[0008] According to one embodiment of the present invention, a structural layout of primary loop of nuclear reactor coolant system includes: a reactor building having a raft base plate defining an upper surface; a pressure vessel in the reactor building and located above the raft base plate; at least one steam generator; a pressurizer; at least one primary coolant pump; and primary coolant pipes for connecting the pressure vessel, the steam generator and the primary coolant pump to form a primary loop, the pressurizer is assembled to the primary coolant pipe, wherein an attitude difference L between a center of the primary coolant pipe connected to the pressure vessel and an upper surface of the raft base plate in the reactor building is 9.7 meters to 10.8 meters.
[0009] According to one aspect of the present invention, the attitude difference L between the center of the primary coolant pipe connected to the pressure vessel and the upper surface of the raft base plate in the reactor building is 10.2 meters to 10.5 meters.
[0010] According to one aspect of the present invention, the attitude difference L between the center of the primary coolant pipe connected to the pressure vessel and the upper surface of the raft base plate in the reactor building is 10.2 meters to 10.4 meters.
[0011] According to one aspect of the present invention, the attitude difference L between the center of the primary coolant pipe connected to the pressure vessel and the upper surface of the raft base plate in the reactor building is 10.4 meters.
[0012] According to one aspect of the present invention, the primary loop of nuclear reactor coolant system includes three steam generators and three primary coolant pumps.
[0013] According to one aspect of the present invention, the three steam generators are set around the pressure vessel, and an angle between two adjacent steam generators is 120 degrees.
[0014] According to one aspect of the present invention, the three primary coolant pumps are set around the pressure vessel, and an angle between two adjacent primary coolant pumps is 120 degrees.
[0015] According to one aspect of the present invention, the primary loop of nuclear reactor coolant system includes one pressurizer which is assembled to a hot leg of the primary coolant pipe.
[0016] According to one aspect of the present invention, the reactor building includes an in-containment refueling water storage tank, and the in-containment refueling water storage tank has a bicyclic pool structure.
[0017] Compared with the prior art, due to the sink arrangement of the primary loop, the primary loop of nuclear reactor coolant system of the present invention can improve the seismic acceleration of the reactor fuel assembly to a level of no less than 0.3g without significant modification to the structure of the reactor fuel assembly, thereby improving the seismic capacity of the reactor and meeting the seismic requirements of the internationally recognized third generation nuclear power technology.
[0018] Other advantages and novel features will be drawn from the following detailed description of preferred embodiment with the attached drawings, in which:
BRIEF DESCRIPTION OF THE DRAWINGS
[0019] Fig. 1 depicts a schematic view of a reactor pressure vessel in a conventional structural layout of a primary loop of nuclear reactor coolant system; [0020] Fig. 2 depicts an exemplary partially cross-sectional view of a structural layout of a primary loop of nuclear reactor coolant system according to one embodiment of the present invention; [0021] Fig. 3 depicts a schematic view of a primary loop in a structural layout of a primary loop of nuclear reactor coolant system according to one embodiment of the present invention; and [0022] Fig. 4 depicts a schematic view of a pressure vessel in a primary loop of nuclear reactor coolant system according to one embodiment of the present invention.
DETAILED DESCRIPTION OF THE INVENTION
[0023] Example embodiments of the present invention will now be described more fully hereinafter with reference to the accompanying drawings, in which some, but not all embodiments of the invention are shown. Indeed, the invention may be embodied in many different forms and should not be construed as limited to the embodiments set forth herein; rather, these embodiments are provided so that this disclosure will satisfy applicable legal requirements. Like reference numerals refer to like elements throughout.
[0024] To improve the seismic level and the safety performance of nuclear power plants and meet the requirements of the primary characteristic parameters of the third generation nuclear power technology, the seismic design requirement of a nuclear power plant needs to be improved to a seismic level of no less than 0.3g. To realize the object, the primary loop, especially the reactor fuel assembly, shall meet the seismic level of no less than 0.3g. In other words, the reactor fuel assembly having a seismic capacity of no less than 0.3g is essential for the whole nuclear power plant having a seismic capacity of no less than 0.3g.
[0025] However, due to the special structure of the reactor fuel assembly, the seismic capacity of the reactor fuel assembly cannot be improved via modifying the structure of the reactor fuel assembly. The seismic capacity of the reactor fuel assembly has to be improved via other means. To avoid significant modification to the structure of the reactor fuel assembly, inventors of the present invention have carried out extensive sensitivity analysis to various major parameters which affect the dynamic response of the nuclear power plant. After repeated algorithm and solution adjustment, the inventors of the present invention found that the attitude difference L between the center of the primary coolant pipe of the primary loop of nuclear reactor coolant system and the upper surface of the raft base plate in the reactor building is the critical parameter which affects the seismic capacity of the reactor. The smaller the attitude difference L is, the stronger the seismic capacity of the reactor has. In view of the foregoing, the seismic capacity of the reactor fuel assembly can be improved via lowering the position of the reactor fuel assembly.
[0026] Based on the above study, the present invention adopts sink arrangement of the reactor, i.e. the sink arrangement of the primary loop, to lower the elevation of the nuclear fuel assembly and reduce the attitude difference between the elevation of the center of the primary coolant pipe and the upper surface of the raft base plate in the reactor building. Via optimizing the structural arrangement scheme, improving the structural rigidity of the reactor building, and reducing the earthquake that the reactor fuel assembly bearing, the primary loop of nuclear reactor coolant system has a seismic capacity of no less than 0.3g.
[0027] Referring to Figs. 2 and 3, the structural layout of the primary loop of nuclear reactor coolant system of the present invention includes a reactor building, a pressure vessel 30, steam generators 36, primary coolant pumps 38, primary coolant pipes 32 and a pressurizer (not shown). The reactor building is provided with a raft base plate. The pressure vessel 30 is arranged at a center of the reactor building and is seated above the raft base plate. The primary coolant pipe 32 is connected to the pressure vessel 30, the steam generator 36 and the primary coolant pump 38, to form a primary loop. In the illustrated embodiment, the three steam generators 36 and the three primary coolant pumps 38 are arranged around the pressure vessel 30, the angle between two adjacent steam generators 36 is 120 degrees, and the angle between two adjacent primary coolant pumps 38 is 120 degrees. The pressurizer is located on the hot leg of the primary coolant pipe 32. In addition, the reactor building is also provided with an in-containment refueling water storage tank 200, and the in-containment refueling water storage tank 200 has a bicyclic pool structure.
[0028] Referring to Fig. 4, the attitude difference L between the center of the primary coolant pipe 32 connected to the pressure vessel 30 and the upper surface 34 of the raft base plate in the reactor building is 10.2 meters to 10.5 meters, and preferably 10.4 meters. In the course of study, it is found that, when the attitude difference L between the center of the primary coolant pipe 32 connected to the pressure vessel 30 and the upper surface 34 of the raft base plate in the reactor building is 9.7 meters to 10.8 meters, the 0.3g seismic requirements of the reactor fuel assemblies can be met. In view of the reactor building and the arrangement of the raft base plate, the attitude difference L of 10.2 meters to 10.5 meters is reasonable and feasible. Further in view of the feasibility of the project (such as equipments, valve installation, and ease of operation), convenience of personnel access (clearance requirements of the floor channel), and the arrangement of the in-containment refueling water storage tank 200 (construction convenience of the outer pool), the attitude difference L of 10.4 meters is the best solution which takes the sink arrangement of the primary loop, the surrounding raft base plate into consideration. According to the present invention, the best attitude difference L between the center of the primary coolant pipe 32 connected to the primary loop and the upper surface 34 of the raft base plate in the reactor building is about 2.0m lower than that in a conventional nuclear power plant.
[0029] In order to cope with the sink arrangement of the primary loop, other structures associated with the present invention are also modified correspondingly. For instance, the structure of the partition wall and the structure of the local wall of the reactor pool are adjusted. Elevation of the cooling ventilation system in containment of the reactor building is adjusted. The main equipments bearing course is improved to a position above the elevation of the operating platform. The pipes connected to the primary loop are moved together with the primary coolant pipes 32. The in-containment refueling water storage tank 200 has bicyclic pool structure, rather than monocyclic pool in conventional nuclear power plant.
[0030] It should be understood by one ordinary skilled in the art that, the smaller the attitude difference L between the center of the primary coolant pipe 32 of the primary loop and the upper surface 34 of the raft base plate in the reactor building, the stronger the seismic capacity of the reactor has. However, the attitude difference L cannot be reduced without limit, because the reactor building of the present invention almost has same layout space and structure as that in a conventional nuclear power plant, so that there will be no unknown problems that cannot be solved in the future. If the attitude difference L is too small, the clear height of the annular space above the outer annular pool 202 is too samll. In this case, there will be no adequate space for valve arrangement and personnel access. It would be very difficult to construct the outer annular pool 202 of the in-containment refueling water storage tank 200 of the reactor building. In addition, too small attitude difference L will lead to unreasonable layout of local area of the surrounding fuel plant and the safety plant, especially the water thickness of the spent fuel in the fuel plant cannot meet the requirement of actual use. Therefore, a limitation is set to the minimum value of the attitude difference L when using the sink arrangement of the primary loop to improve the seismic capacity of the reactor fuel assembly.
[0031] Compared with the prior art, due to the sink arrangement of the primary loop, the attitude difference L between the center of the primary coolant pipe 32 of the primary loop and the upper surface 34 of the raft base plate in the reactor building is no more than 10.4 meters, which is 2.0 meters less than the attitude difference of the conventional nuclear power plant. Therefore, the seismic acceleration of the reactor fuel assembly can be improved to a level of no less than 0.3g without significant modification to the structure of the reactor fuel assembly, thereby improving the seismic capacity of the reactor and meeting the seismic requirements of the internationally recognized third generation nuclear power technology.
[0032] The primary loop of nuclear reactor coolant system of the present invention at least has the following advantages: 1) Due to the sink arrangement of the primary loop, the seismic acceleration of the reactor is improved to a level of no less than 0.3g. During selecting the site for the nuclear power plant, the range of site selection is wider and the seismic margin is larger, so as to meet different seismic requirements of different sites. 2) Seismic capacity and anti-disaster ability of the nuclear power plant are improved remarkably. The safety performances of the nuclear power plant are improved remarkably, which can eliminate public doubts and fears to the safety performances of the nuclear power plant. The seismic acceleration of the reactor is improved from 0.2g to no less than 0.3g, and the seismic acceleration of the nuclear power plant is correspondingly improved from 0.2g to no less than 0.3g. Therefore, the nuclear power plant has stronger ability against external disaster, i.e. earthquake, and the public has much more confidence and acceptance to the safety performances of the nuclear power plant. 3) The seismic design of the nuclear power plant meets the seismic requirements of the internationally recognized third generation nuclear power technology and meets the requirement of EUR and URD. The seismic acceleration of the reactor according to the present invention is of no less than 0.3g. Compared with the seismic acceleration of 0.25g and 0.3g of the known third generation nuclear power technology, the seismic acceleration in accordance with the present invention can meet the requirements of the internationally recognized third generation nuclear power users. 4) The seismic structure of the reactor fuel assembly is simplified, significant design modification of the reactor fuel assembly to improve the seismic capacity is avoided, and the design time of the fuel assembly structure is shortened.
[0033] While the present invention has been illustrated by the above description of the preferred embodiment thereof, while the preferred embodiment has been described in considerable detail, it is not intended to restrict or in any way limit the scope of the appended claims to such details. Additional advantages and modifications within the spirit and scope of the present invention will readily appear to those ordinary skilled in the art. Consequently, the present invention is not limited to the specific details and the illustrative examples as shown and described.
Claims (9)
1. A structural layout of primary loop of nuclear reactor coolant system, comprising: a reactor building having a raft base plate defining an upper surface; a pressure vessel in the reactor building and located above the raft base plate; at least one steam generator; a pressurizer; at least one primary coolant pump; and primary coolant pipes for connecting the pressure vessel, the steam generator and the primary coolant pump to form a primary loop, wherein the pressurizer is assembled to the primary coolant pipe, characterized in that an attitude difference L between a center of the primary coolant pipe connected to the pressure vessel and an upper surface of the raft base plate is 9.7 meters to 10.8 meters.
2. The structural layout of primary loop of nuclear reactor coolant system of claim 1, characterized in that the attitude difference L between the center of the primary coolant pipe connected to the pressure vessel and the upper surface of the raft base plate is 10.2 meters to 10.5 meters.
3. The structural layout of primary loop of nuclear reactor coolant system of claim 1, characterized in that the attitude difference L between the center of the primary coolant pipe connected to the pressure vessel and the upper surface of the raft base plate is 10.2 meters to 10.4 meters.
4. The structural layout of primary loop of nuclear reactor coolant system of claim 1, characterized in that the attitude difference L between the center of the primary coolant pipe connected to the pressure vessel and the upper surface of the raft base plate is 10.4 meters.
5. The structural layout of primary loop of nuclear reactor coolant system of any one of claims 1 to 4, characterized in that the primary loop of nuclear reactor coolant system comprises three steam generators and three primary coolant pumps.
6. The structural layout of primary loop of nuclear reactor coolant system of claim 5, characterized in that the three steam generators are set around the pressure vessel and an angle between two adjacent steam generators is 120 degrees.
7. The structural layout of primary loop of nuclear reactor coolant system of claim 5, characterized in that the three primary coolant pumps are set around the pressure vessel and an angle between two adjacent primary coolant pumps is 120 degrees.
8. The structural layout of primary loop of nuclear reactor coolant system of any one of claims 1 to 4, characterized in that the primary loop of nuclear reactor coolant system comprises one pressurizer assembled to a hot leg of the primary coolant pipe.
9. The structural layout of primary loop of nuclear reactor coolant system of any one of claims 1 to 4, characterized in that the reactor building comprises an in-containment refueling water storage tank, and the in-containment refueling water storage tank has a bicyclic pool structure.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510505380.9A CN106469578B (en) | 2015-08-18 | 2015-08-18 | The arrangement of nuclear power plant reactor coolant system major loop |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| GB201521984D0 GB201521984D0 (en) | 2016-01-27 |
| GB2541475A GB2541475A (en) | 2017-02-22 |
| GB2541475B true GB2541475B (en) | 2019-07-31 |
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| Application Number | Title | Priority Date | Filing Date |
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| GB1521984.3A Active GB2541475B (en) | 2015-08-18 | 2015-12-14 | Structural layout of primary loop of nuclear reactor coolant system |
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| CN (1) | CN106469578B (en) |
| GB (1) | GB2541475B (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108278997B (en) * | 2017-12-29 | 2021-10-19 | 中国核工业二三建设有限公司 | Main equipment control network of nuclear power station and establishment method thereof |
| CN110853784B (en) * | 2019-11-19 | 2022-07-29 | 中国核动力研究设计院 | Pressurized water reactor nuclear power plant stabiliser bearing structure |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4518561A (en) * | 1981-02-10 | 1985-05-21 | Framatome Et Cie | Reactor building |
| US6570950B1 (en) * | 2002-03-11 | 2003-05-27 | Westinghouse Electric Company Llc | Nuclear plant containment with prefabricated component support structure |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5610962A (en) * | 1995-09-22 | 1997-03-11 | General Electric Company | Construction of nuclear power plants on deep rock overlain by weak soil deposits |
| JP5842218B2 (en) * | 2011-06-07 | 2016-01-13 | 国立大学法人東北大学 | Powerless reactor cooling system |
| JP5750032B2 (en) * | 2011-11-30 | 2015-07-15 | 日立Ｇｅニュークリア・エナジー株式会社 | Boiling water reactor |
| JP5898604B2 (en) * | 2012-10-31 | 2016-04-06 | 日立Ｇｅニュークリア・エナジー株式会社 | Safety equipment for nuclear power plants |
| CN203338768U (en) * | 2013-07-26 | 2013-12-11 | 中广核工程有限公司 | Protective device for nuclear power plant reactor pressure vessel |
-
2015
- 2015-08-18 CN CN201510505380.9A patent/CN106469578B/en active Active
- 2015-12-14 GB GB1521984.3A patent/GB2541475B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4518561A (en) * | 1981-02-10 | 1985-05-21 | Framatome Et Cie | Reactor building |
| US6570950B1 (en) * | 2002-03-11 | 2003-05-27 | Westinghouse Electric Company Llc | Nuclear plant containment with prefabricated component support structure |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106469578B (en) | 2017-11-17 |
| GB201521984D0 (en) | 2016-01-27 |
| CN106469578A (en) | 2017-03-01 |
| GB2541475A (en) | 2017-02-22 |
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