CN104143366A - Passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method - Google Patents
Passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method Download PDFInfo
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- CN104143366A CN104143366A CN201310172943.8A CN201310172943A CN104143366A CN 104143366 A CN104143366 A CN 104143366A CN 201310172943 A CN201310172943 A CN 201310172943A CN 104143366 A CN104143366 A CN 104143366A
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- main pump
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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
Abstract
The invention belongs to the technical field of passive pressurized water reactors, in particular to a passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method. The passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method comprises the following steps that firstly, after a user logs into the CFXBlademodeler software to input the number of blades of a main pump and blade profile parameters, models of an impeller and guide vanes of the main pump are established, and the models of the impeller and the guide vanes are exported in the general formats such as *.IGS; secondly, the user logs into the Pro/Engineer software, and models of a lower cavity of a steam generator and a pump shell are established according to design drawings of the lower cavity of the steam generator and the pump shell of the main pump and are exported in the general format such as *.IGS; thirdly, the models of the impeller and the guide vanes of the main pump and the models of the lower cavity of the steam generator and the pump shell are imported into the Gambit mesh generation software so that combination of the analysis models and mesh generation can be conducted, and a complete analysis model is exported; fourthly, the analysis model is imported into the Fluent solver for analysis, and then a result is obtained. By the adoption of the passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method, the reliability, the safety and the economical performance of a power plant can be improved.
Description
Technical field
The invention belongs to passive PWR technical field, be specifically related to a kind of passive PWR Steam Generators in NPP-main pump coupling flow field analysis method.
Background technology
Tradition PWR nuclear power plant (main pump) reactor coolant pump connected with being connected by transition section of steam generator, and the flow field of steam generator lower chambers and the flow field of main pump do not influence each other.Under such configuration, the hydraulic performance of main pump impeller parts only need to meet the needs of flow-lift, and the flow field of steam generator lower chambers does not need the impact of considering that main pump brings yet.
The main pump (shielding electrodynamic pump) of AP series passive PWR nuclear power plant is directly welded on steam generator low head, the effect of mixing due to main pump impeller, likely in main pump inlet part flow field, produce whirlpool, and then make the crushing in steam generator exit increase and may affect long-term stability operation and the hydraulic efficiency of main pump.As most important two equipment in PWR nuclear power plant, efficient, the stable operation of main pump and steam generator, all have a significant impact for safety and the economy of nuclear power plant.Therefore in main pump and steam generator design process, must be studied this problem.
If the method for adoption rate model test is carried out the research of this problem, not only testing expenses are very high, and the universality of test findings is not high, parameter and equipment size are slightly revised test findings will be no longer applicable, cannot meet the requirement of large-scale advanced passive PWR nuclear power plant seriation exploitation.Therefore, must seek a kind of accurately, the method for steam generator lower chambers-main pump flow field coupling analysis easily.
Summary of the invention
The object of the present invention is to provide a kind of passive PWR Steam Generators in NPP-main pump coupling flow field analysis method, to solve problem how to obtain AP series passive PWR Steam Generators in NPP lower chambers and main pump coupling flow field situation, and then for equipment design provides support, to improve reliability, security and the economy of power plant.
For achieving the above object, the technical solution used in the present invention is:
Passive PWR Steam Generators in NPP-main pump coupling flow field analysis method, comprises the steps:
Step 1: enter CFX Blademodeler software, after the number of blade of input main pump, blade profile parameters data, set up the model of main pump impeller and stator, and derive the model of impeller and stator with general formats such as * .IGS forms;
Step 2: enter Pro/Engineer software, set up the model of steam generator lower chambers and pump case according to the design drawing of steam generator lower chambers and main pump pump case, and derive with general formats such as * .IGS forms;
Step 3: the model of the model of main pump impeller and stator and steam generator lower chambers and pump case is jointly imported in Gambit grid division software and carries out the combination of analytical model and the division of grid, and derive perfect analytical model;
Step 4: analytical model is imported and analyzes in Fluent solver and obtain a result.
The obtained beneficial effect of the present invention is:
The present invention can obtain the coupling flow field of AP series passive PWR Steam Generators in NPP lower chambers and main pump very easily.And then for equipment design provides support, to improve reliability, security and the economy of power plant:
(1) the present invention utilizes the feature of CFX Blademodeler and Pro/Engineer, respectively the other parts outside main pump hydraulic parts and hydraulic part is carried out to modeling, and modeling work is simplified greatly, and the time that whole method is expended shortens greatly.
(2) analysis result is accurately credible: the precision of analysis of mixing the main pump hydraulic parts in source as whole steam generator lower chambers-main pump flow field has vital impact to the accuracy of whole flow field analysis.Deviation is in 5%, so analysis result confidence level is very high for the main pump lift calculating by intercepting main pump inlet and outlet pressure value and main pump rated lift (through main pump hydraulic verification experimental verification).
Embodiment
Below in conjunction with the drawings and specific embodiments, the present invention is described in detail.
Passive PWR Steam Generators in NPP of the present invention-main pump coupling flow field analysis method comprises the steps:
Step 1: enter CFX Blademodeler software, after the data such as blade (stator) number of input main pump, blade profile parameters, set up the model of main pump impeller and stator, and derive the model of impeller and stator with general formats such as * .IGS forms;
Step 2: enter Pro/Engineer software, set up the model of steam generator lower chambers and pump case according to the design drawing of steam generator lower chambers and main pump pump case, and derive with general formats such as * .IGS forms;
Step 3: the model of the model of main pump impeller and stator and steam generator lower chambers and pump case is jointly imported in Gambit grid division software and carries out the combination of analytical model and the division of grid, and derive perfect analytical model;
Step 4: analytical model is imported and analyzes in Fluent solver and obtain a result.
Claims (1)
1. passive PWR Steam Generators in NPP-main pump coupling flow field analysis method, is characterized in that: the method comprises the steps:
Step 1: enter CFX Blademodeler software, after the number of blade of input main pump, blade profile parameters data, set up the model of main pump impeller and stator, and derive the model of impeller and stator with general formats such as * .IGS forms;
Step 2: enter Pro/Engineer software, set up the model of steam generator lower chambers and pump case according to the design drawing of steam generator lower chambers and main pump pump case, and derive with general formats such as * .IGS forms;
Step 3: the model of the model of main pump impeller and stator and steam generator lower chambers and pump case is jointly imported in Gambit grid division software and carries out the combination of analytical model and the division of grid, and derive perfect analytical model;
Step 4: analytical model is imported and analyzes in Fluent solver and obtain a result.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310172943.8A CN104143366A (en) | 2013-05-10 | 2013-05-10 | Passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201310172943.8A CN104143366A (en) | 2013-05-10 | 2013-05-10 | Passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method |
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| Publication Number | Publication Date |
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| CN104143366A true CN104143366A (en) | 2014-11-12 |
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| CN201310172943.8A Pending CN104143366A (en) | 2013-05-10 | 2013-05-10 | Passive pressurized water reactor nuclear power plant steam generator-main pump coupling flow field analysis method |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105022895A (en) * | 2015-08-14 | 2015-11-04 | 上海核工程研究设计院 | System-level CFD analytical method of PumpLinx |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3979914A (en) * | 1974-06-06 | 1976-09-14 | Sulzer Brothers Limited | Process and apparatus for superheating partly expanded steam |
| US4057034A (en) * | 1975-05-15 | 1977-11-08 | Westinghouse Electric Corporation | Process fluid cooling system |
| US4619809A (en) * | 1983-03-30 | 1986-10-28 | The Babcock & Wilcox Company | Steam generation and reheat apparatus |
| US6367430B1 (en) * | 2000-03-21 | 2002-04-09 | Babcock & Wilcox Canada, Ltd. | Scalloped lattice bar nuclear steam generator tube supports |
-
2013
- 2013-05-10 CN CN201310172943.8A patent/CN104143366A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3979914A (en) * | 1974-06-06 | 1976-09-14 | Sulzer Brothers Limited | Process and apparatus for superheating partly expanded steam |
| US4057034A (en) * | 1975-05-15 | 1977-11-08 | Westinghouse Electric Corporation | Process fluid cooling system |
| US4619809A (en) * | 1983-03-30 | 1986-10-28 | The Babcock & Wilcox Company | Steam generation and reheat apparatus |
| US6367430B1 (en) * | 2000-03-21 | 2002-04-09 | Babcock & Wilcox Canada, Ltd. | Scalloped lattice bar nuclear steam generator tube supports |
Non-Patent Citations (1)
| Title |
|---|
| 夏栓: "AP1000核岛主泵流场数值模拟", 《核技术》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105022895A (en) * | 2015-08-14 | 2015-11-04 | 上海核工程研究设计院 | System-level CFD analytical method of PumpLinx |
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Application publication date: 20141112 |