CN110531635A - One kind being based on the fast reactor main pump circulation passage Modeling Calculation method of " virtual valve " - Google Patents
One kind being based on the fast reactor main pump circulation passage Modeling Calculation method of " virtual valve " Download PDFInfo
- Publication number
- CN110531635A CN110531635A CN201910609570.3A CN201910609570A CN110531635A CN 110531635 A CN110531635 A CN 110531635A CN 201910609570 A CN201910609570 A CN 201910609570A CN 110531635 A CN110531635 A CN 110531635A
- Authority
- CN
- China
- Prior art keywords
- fast reactor
- face
- heap
- main pump
- fluid
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G05—CONTROLLING; REGULATING
- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B17/00—Systems involving the use of models or simulators of said systems
- G05B17/02—Systems involving the use of models or simulators of said systems electric
Abstract
The invention discloses the fast reactor main pump circulation passage Modeling Calculation methods that the one kind for belonging to pile Three-dimensional simulation technical field is based on " virtual valve ".Based on pool type natrium cold fast reactor, Rational Simplification is carried out to heap container and in-pile component, establishes the fast reactor model of three-dimensional pool；Three-dimensional thermal technology's fluid transient in the fast reactor heap under various working can be carried out using a model to calculate, by the attribute for changing main pump and each face for being connected to coupling module between pressure pipe, the simple change of part is carried out for the face attribute of the connection coupling module of primary Ioops main pump, can in accurate simulation heap flow process transient condition, three-dimensional thermal technology's transient state that fluid in the analysis of fast reactor primary Ioops emergency system and heap is carried out under all kinds of operating conditions calculates, including operating normally, it is contemplated that run case and accident conditions.The present invention greatly reduces the workload of modeling and calculating.It realizes the calculating that multiple operating conditions can be completed using a set of grid file, provides support and foundation for fast reactor design and safety analysis.
Description
Technical field
The invention belongs to fast reactor Three-dimensional simulation technical field, in particular to a kind of fast reactor master for being based on " virtual valve "
Pump circulation passage Modeling Calculation method.Specifically one kind can be used for carrying out fast reactor primary Ioops emergency system under all kinds of operating conditions
Three-dimensional thermal technology's transient state of fluid calculates in analysis and heap, including operates normally, it is contemplated that run case and accident conditions.
Background technique
Fast reactor is an important direction of forth generation reactor, and fast reactor can consume the nuke rubbish of thermal-neutron reactor generation, benefit
With the not fissile nuclide being widely present in the unavailable nature of thermal-neutron reactor and generate thermal energy.It is fast with pool type natrium cold
For heap, system includes primary, secondary sodium loop and sodium-water (vapour) heat exchanger, by reactor core, primary Ioops coolant pump and its
Outlet conduit and intermediate heat exchanger are arranged in a sodium pond, form integral structure.Liquid metal sodium is as primary Ioops
Coolant and secondary circuit catalyst carrier.Reator body is in integrated arrangement.Primary tank top is argon gas cavity, isolation primary Ioops sodium and
Outside atmosphere.Primary Ioops have two loops in parallel.There are a main circulation pump and two intermediate heat exchangers in each loop.
Structure is sufficiently complex in heap, and the structure size difference of different in-pile components is huge, and logarithm simulation, which calculates, proposes very big choose
War.
Many one-dimensional, two-dimensional system software analysis were carried out to primary Ioops system in heap both at home and abroad, such as Chinese atomic energy
The FASYS program for pool type sodium cooled fast reactor accident analysis of research institute's exploitation, the THPCS of Xi'an Communications University's exploitation,
THACS, there are also external some crash analysis software such as SSC-L, SSC-K, SIMMER etc., and what is obtained is all one-dimensional or two-dimentional
Network analysis result.But thermal-hydraulic characteristic has apparent three-dimensional character in pool fast reactor heap, needs to carry out detailed three
Tie up transient response simulation.It is mostly local single component, such as Zhang Xiaolong is ground at present both at home and abroad to the three-dimensional computations of fast reactor
Study carefully and restrain influence of the different arrangement modes to its internal temperature and flow field Temperature Distribution inside intermediate heat exchanger, Faruk etc. is ground
Study carefully the influence of the different location and different shape of case assembly internal blocking appearance to temperature field, flow field in box, there are also to pond
The primary tank cooling system of formula fast reactor carries out three-dimensional, two-dimensional calculating and Brendan et al. and establishes for the primary Ioops of fast reactor
Simple model carries out the thermal stratification analysis in primary Ioops.The coupled simulation of heap complete for pool fast reactor, A.Toti etc.
People is directed to research reactor MYRRHA, has carried out the three-dimensional computations in the case where losing water supply transient state using RELAP5 and FLUENT,
The method that U.Parthasarathy etc. is combined using business software with the one-dimensional software of secondary circuit calculates the waste heat of PHENIX heap
The effect of discharge system, Xu Yijun et al. have carried out the calculating under modeling and transient state, but its model phase to the cold and hot plenums of CEFR
Simplification is more for, can not accurately simulate the flow behavior of fluid in heap under various working.Lack both at home and abroad to fast at present
Heap carries out the precedent of full heap, detailed Three dimensional transient simulation.
The present invention provides a kind of fast reactor main pump circulation passage Modeling Calculation method for being based on " virtual valve ", with pool type natrium cold
For fast reactor, by the different disposal to different accident downstream conditions, establishing a nested grid, to can be carried out pool type natrium cold fast
The three-dimensional thermal technology's transient state piled up under all kinds of accident conditions calculates, and can greatly reduce the workload of modification grid and modeling.Such as
When occurring to lose water supply accident, two primary Ioops main pumps can be operated normally, but reactor core wants shutdown at this time, in order to match heap
Interior variation, the flow of primary Ioops main pump are also to change therewith, this when, the entrance of main pump was exactly for model
Constant flow entrance boundary condition.When a pump axis accident occurs, wherein a main pump boundary condition is constant, process is another
The fluid thermal parameter of platform main pump is no longer just known boundary condition, and needing to calculate can just access.Station blackout is occurring
When accident, two main pump running downs of primary Ioops after running down, without entrance in heap, establish the Natural Circulation in heap, warp
Cross the fluid thermal parameter of two pumps be all it is unknown, two pumps all cannot function as boundary condition and be calculated.Result of study can be with
Support and foundation are provided for the design of fast reactor.
Summary of the invention
Fast reactor main pump circulation passage Modeling Calculation method the object of the present invention is to provide one kind based on " virtual valve ",
It is characterized in that, primary Ioops are by two main pumps 7, connection coupling module 13, pressure pipe 5, grid plate header 3 in the fast reactor container
It connect the pool type natrium cold fast reactor primary Ioops of composition with reactor core 2, is a closed system, and the connection coupling module 13 on both sides
The face b, the face d be arranged to inside face, the face a, the face c are arranged to solid face；The face e is the channel that fluid enters pump from cold drop；One time
The calculating of road three-dimensional thermal technology's fluid transient includes the following steps:
Step 1, in two main pumps of primary Ioops and pressure pipe joint, each setting one for boundary condition conversion
It is connected to coupling module, which is connect by interface in fluent with whole fast reactor model, passed through
The noodles type that interface is adjusted in fluent changes the traffic ingress of fast reactor model or closes traffic ingress, simplifies
Grid model, so that a set of grid model can be used in the calculating of various working；
Step 2, in pool type natrium cold fast reactor, Rational Simplification is carried out to heap container and in-pile component, establishing includes that center is surveyed
Measure 6, two primary Ioops main pumps 7 of the interior bearing of column 1, reactor core 2, grid plate header 3, primary tank 4, pressure pipe 5, heap, overflow window 8, biology
Shield the outer biological shielding column 11 of column 9, intermediate heat exchanger 10, reactor core, reactor core shielding 12, connection coupling module 13, core meltdown
The pool type natrium cold fast reactor model of the detailed three-dimensional of collector and crowded sodium device；The model being capable of flow process in accurate simulation heap
Transient condition, obtaining fluid three-dimensional thermal technology's hydraulic parameters in detailed heap is fluid temperature (F.T.), pressure, the speed in heap everywhere；
Step 3, determine that the physical parameter of sodium fluid, the physical parameter of sodium are the density of the liquid sodium inputted before calculating, glue
Degree, specific heat capacity, after then calculating again, three-dimensional thermal technology's hydraulic parameters of fluid include the temperature of fluid, speed everywhere in obtained heap
Degree, pressure；And the physical parameter of each component materials: become in fluent using the density of sodium, specific heat capacity, viscosity with temperature
Change；The body cold source of intermediate heat exchanger IHX and residual heat removal exchanger DHX, the body heat source of reactor core are by writing fluent
In the Users-defined fuction program that carries control, thus control each portion of pool type natrium cold fast reactor under different operating conditions
The power of part changes over time.
The boundary condition of the fast reactor model: giving entrance fluid in the entrance of pressure pipe, above pressure pipe, inside pump
It is exported to pressure.
It is described to need artificial given entrance when calculating stable state, the primary Ioops sodium flowing in heap could be simulated, is entered
The impeller outlet of main pump, that is, the face c that main pump and pressure pipe connect in model is arranged in mouth, and outlet is arranged in realistic model
In main pump the face impeller eye a, and be set as pressure export, balance primary Ioops flow；Under different accident conditions, lead to
The each face attribute and external udf of crossing change changeover portion change the boundary of different operating conditions to the control of inlet flow rate and temperature
Condition.
The beneficial effects of the invention are as follows use a model that can carry out the Three Dimensional Thermal in the fast reactor heap under various working
Work fluid transient calculates, by changing the attribute of main pump and each face for being connected to coupling module between pressure pipe, for primary Ioops
The face attribute of the connection coupling module of main pump carries out the simple change of part, so that it may realize the three-dimensional meter under the operating condition
It calculates, greatly reduces the workload of modeling and calculating.Different boundary conditions can be provided under different operating conditions, realized and used one
The calculating of multiple operating conditions can be completed in nested grid file, provides support and foundation for fast reactor design and safety analysis.
Detailed description of the invention
Fig. 1 is the pool fast reactor model schematic diagram established.
Fig. 2 primary Ioops coolant glide path schematic diagram.
The mobility status of internal flow at coupling module is connected between Fig. 3 main pump and pressure pipe, wherein (a) transition is connected to coupling
Mold block Provisioning Policy 1；(b) transition is connected to coupling module Provisioning Policy 2；
Specific embodiment
The present invention provides a kind of fast reactor main pump circulation passage Modeling Calculation method for being based on " virtual valve ", below with reference to attached
Figure is explained the present invention.
Fig. 1 show pool fast reactor model schematic diagram.The pool fast reactor of foundation includes center measurement column 1, reactor core 2, screen
6, two primary Ioops main pumps 7 of bearing, overflow window 8, biological shielding column 9, intermediate heat are handed in header 3, primary tank 4, pressure pipe 5, heap
Parallel operation 10, reactor core outer biological shielding column 11, are connected to coupling module 13, core meltdown collector and crowded sodium device at reactor core shielding 12
The pool type natrium cold fast reactor model of detailed three-dimensional；In the fast reactor model of built three-dimensional pool, fluid passes through main pump 7, pressure pipe
After 5 enter grid plate headers 3, carry out assignment of traffic, most fluid enters reactor core 2 and is heated, after the outflow of reactor core 2 through by
Overflow window 8 on biological shielding column 9 enters hot pool area, enters after intermediate heat exchanger 10 is cooled afterwards and sends cold drop back to, then by
Main pump 7 squeezes into reactor core 2, and the route of fluid flowing is as illustrated by the arrows in fig. 1.
Fig. 2 show primary Ioops coolant glide path schematic diagram.Primary Ioops are by two main pumps 7, even in fast reactor container
Logical coupling module 13, pressure pipe 5, grid plate header 3 connect the pool type natrium cold fast reactor primary Ioops of composition with reactor core 2, are a closings
System, and the face b, the face d of the connection coupling module 13 on both sides are arranged to inside face, the face a, the face c are arranged to solid face；The face e
It is the channel that fluid enters pump from cold drop；The calculating of primary Ioops three-dimensional thermal technology's fluid transient includes the following steps:
Step 1, in two main pumps of primary Ioops and pressure pipe joint, each setting one for boundary condition conversion
It is connected to coupling module 13, which is connect in fluent by interface with whole fast reactor model
(as shown in Figure 1, 2), by adjusting the noodles type of interface in fluent, the b of the connection coupling module 13 on both sides
Face, the face d are arranged to inside face, and the face a, the face c are arranged to solid face；Change the traffic ingress of fast reactor model or closes flow
Entrance simplifies grid model, so that a set of grid model can be used in the calculating of various working；
Step 2, in pool type natrium cold fast reactor, Rational Simplification is carried out to heap container and in-pile component, which can be accurate
The transient condition for simulating flow process in heap, obtaining fluid three-dimensional thermal technology's hydraulic parameters in detailed heap is the stream in heap everywhere
Temperature, pressure, speed；Under the operating condition of normal reactor operation, primary Ioops main pump be transported to fluid temperature (F.T.) in reactor core and
Flow be all it is given, at this time set the pressure pipe top annular face c as shown in Figure 2 to the flow border entries of model, a
Face is set as the outlet of model.It is by external udf process control by the flow that the face c enters system, temperature is to pass through a
Although the fluid that the temperature that face obtains is assigned to flow through the face c to be artificially to give entrance in model, inlet is to obtain
The temperature in the exit taken, and pressure boundary outlet is set by outlet, the flow in balance system, therefore the stream in system
Amount and temperature are all matched.
Step 3, determine that the physical parameter of sodium fluid, the physical parameter of sodium are the density of the liquid sodium inputted before calculating, glue
Degree, specific heat capacity, after then calculating again, three-dimensional thermal technology's hydraulic parameters of fluid include the temperature of fluid, speed everywhere in obtained heap
Degree, pressure；And the physical parameter of each component materials: become in fluent using the density of sodium, specific heat capacity, viscosity with temperature
Change；The body cold source of intermediate heat exchanger IHX and residual heat removal exchanger DHX, the body heat source of reactor core are by writing fluent
In the Users-defined fuction program that carries control, thus control each portion of pool type natrium cold fast reactor under different operating conditions
The power of part changes over time.As shown in figure 3, the power of IHX and core changes over time under accident conditions, at this
In calculative strategy, and controlled by external udf program, do not need modification cas file, it is only necessary to change udf journey
Corresponding function in sequence, so that it may which the power for meeting IHX and core changes according to the rule that corresponding operating condition needs.
Embodiment
By adjusting each face attribute of the T-type connection coupling module 13 between main pump 7 and pressure pipe 5, so that it may not
In the case where changing grid, different boundary conditions is set, carries out the calculating of different operating conditions, the concrete operations in calculating:
1) steady state condition: when carrying out stable state calculating, the face c is arranged to the entrance boundary of the fixed temperature of constant flow, and the face a is that pressure goes out
Mouth boundary, remaining each face for being connected to coupling module is set as wall；
2) transient condition 1, steam generator secondary side lose water supply accident: when the accident occurs, steam generator can not band
The heat of secondary circuit intermediate heat exchanger 10 is walked, correspondingly, the hot sodium of primary Ioops is unable to get effective cooling, in primary Ioops
Between 10 cooling power of heat exchanger decline rapidly.It is lost in several seconds to water signal receiving steam generator, control rod insertion,
Reactor core 2 start shutdown, in order to match the variation of power in heap, the flow of primary Ioops main pump 7 is gradually reduced, fluid temperature (F.T.) also with
Temperature change in cold drop, therefore under the transient condition, the flow and temperature of entrance are to change over time, in udf program
In, the face a, the face b are arranged to the traffic ingress boundary condition that flow changes over time, the mean temperature in the face a is taken to be assigned to pass through c
Face enters the fluid of system, and the setting of two main pumps 7 and pressure pipe 5 is not always the case, in fluid flow direction such as Fig. 3 therein
(a) shown in.
3) transient condition 2, one main pump axis accident of primary Ioops: when the accident occurs, it is assumed that the second main pump of primary Ioops
7 block (on the right of Fig. 2), and fluid can not be given to provide kinetic energy, the second main pump 7 become one can accommodate that fluid passes through have
The channel of certain resistance.The face a of the second main pump 7 is arranged to solid face at this time, the face b and the face d that will be connected to coupling module 13
Become inside face, allows fluid to pass through from the face e, in this way in the connection coupling module of the second main pump 7, be formed one
Channel, fluid is in the direction wherein flowed as shown in the arrow of (b) in Fig. 3.Another the first intact main pump 7 is then according to Fig. 3
In set-up mode shown in (a), give inlet flow rate boundary.
4) transient condition 3, the whole audience loss of power accident: when the accident occurs, entire power plant loses power supply, and two main pumps 7 all can
It runs out of steam, starts running down.Within the time of 7 running down of main pump, the connection coupling module 13 of two main pumps 7 is all made of in Fig. 3
(a) setting shown in gives inlet flow rate according to flow running down curve；After running down stops, connection coupling module 13 takes Fig. 3
In be arranged shown in (b), the face b, the face d of the connection coupling module on both sides are arranged to inside face, the face a, the face c are arranged to reality
Dignity can allow fluid to flow in main pump 7, meet the setting of Natural Circulation in heap.
Claims (3)
1. the fast reactor main pump circulation passage Modeling Calculation method that one kind is based on " virtual valve ", which is characterized in that the fast reactor container
Interior primary Ioops are by two main pumps (7), connection coupling module (13), pressure pipe (5), grid plate header (3) and reactor core (2) connection group
At pool type natrium cold fast reactor primary Ioops, be a closed system, and the face b the connection coupling module (13) on both sides, the setting of the face d
At inside face, the face a, the face c are arranged to solid face；The face e is the channel that fluid enters pump from cold drop；Primary Ioops three-dimensional thermal-hydraulic
The calculating of transient state includes the following steps:
Step 1, in two main pumps of primary Ioops and pressure pipe joint, connection coupling of each setting one for boundary condition conversion
Block is molded, which is connect in fluent by interface with whole fast reactor model, by fluent
The middle noodles type for adjusting interface changes the traffic ingress of fast reactor model or closes traffic ingress, simplifies grid mould
Type, so that a set of grid model can be used in the calculating of various working；
Step 2, in pool type natrium cold fast reactor, Rational Simplification is carried out to heap container and in-pile component, establishing includes center measurement column
(1), (6) are supported in reactor core (2), grid plate header (3), primary tank (4), pressure pipe (5), heap, two primary Ioops main pumps (7), are overflow
Flow window (8), biological shielding column (9), intermediate heat exchanger (10), the outer biological shielding column (11) of reactor core, reactor core shielding (12), connection
The pool type natrium cold fast reactor model of the detailed three-dimensional of coupling module (13), core meltdown collector and crowded sodium device；The model can
The transient condition of flow process in accurate simulation heap, obtain fluid three-dimensional thermal technology's hydraulic parameters in detailed heap be in heap everywhere
Fluid temperature (F.T.), pressure, speed；
Step 3, determine that the physical parameter of sodium fluid, the physical parameter of sodium are density, the viscosity, ratio of the liquid sodium inputted before calculating
Thermal capacitance, after then calculating again, three-dimensional thermal technology's hydraulic parameters of fluid include the temperature, speed, pressure of fluid everywhere in obtained heap
By force；And the physical parameter of each component materials: using the density of sodium, specific heat capacity, viscosity with temperature variation in fluent；It is intermediate
The body cold source of heat exchanger IHX and residual heat removal exchanger DHX, the body heat source of reactor core are carried by writing in fluent
Users-defined fuction program controls, and thus controls the power of each component of pool type natrium cold fast reactor under different operating conditions
It changes over time.
2. being based on the fast reactor main pump circulation passage Modeling Calculation method of " virtual valve " according to claim 1, which is characterized in that
The boundary condition of the fast reactor model: giving entrance fluid in the entrance of pressure pipe, goes out above pressure pipe, inside pump to pressure
Mouthful.
3. being based on the fast reactor main pump circulation passage Modeling Calculation method of " virtual valve " according to claim 1, which is characterized in that
When calculating the stable state of primary Ioops three-dimensional thermal-hydraulic, artificial given entrance is needed, the primary Ioops sodium stream in heap could be simulated
Dynamic, the impeller outlet of main pump is arranged in entrance, that is, the face c that main pump and pressure pipe connect in model, and outlet is arranged in reality
The face impeller eye a of main pump in model, and it is set as pressure export, balance primary Ioops flow；Under different accident conditions,
Change the boundary of different operating conditions to the control of inlet flow rate and temperature by each face attribute and external udf that change changeover portion
Condition.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910609570.3A CN110531635B (en) | 2019-07-08 | 2019-07-08 | Fast reactor main pump flow channel modeling calculation method based on virtual valve |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910609570.3A CN110531635B (en) | 2019-07-08 | 2019-07-08 | Fast reactor main pump flow channel modeling calculation method based on virtual valve |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110531635A true CN110531635A (en) | 2019-12-03 |
| CN110531635B CN110531635B (en) | 2020-10-23 |
Family
ID=68659887
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910609570.3A Active CN110531635B (en) | 2019-07-08 | 2019-07-08 | Fast reactor main pump flow channel modeling calculation method based on virtual valve |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110531635B (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112687408A (en) * | 2020-12-24 | 2021-04-20 | 中国原子能科学研究院 | Experimental model for sodium-cooled pool type fast reactor natural circulation experiment |
| CN113063816A (en) * | 2021-03-23 | 2021-07-02 | 华北电力大学 | Test bench for researching thermal oscillation of central column of fast reactor plug |
| CN113343597A (en) * | 2021-06-01 | 2021-09-03 | 潍柴动力股份有限公司 | Method and device for calculating virtual pressure behind throttle valve |
| CN113657049A (en) * | 2021-08-17 | 2021-11-16 | 哈尔滨工程大学 | Rapid simulation method for heat transfer and flow of main coolant system of pool type sodium-cooled fast reactor |
Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2007025235A1 (en) * | 2005-08-26 | 2007-03-01 | Ppg Industries Ohio, Inc. | Method and apparatus for the production of ultrafine silica particles from solid silica powder and related coating compositions |
| CN101620892A (en) * | 2009-07-30 | 2010-01-06 | 华北电力大学 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
| KR20100120529A (en) * | 2009-05-06 | 2010-11-16 | 한국원자력연구원 | Device for heating a simulated core in sodium cooled fast reactor system |
| WO2013033144A2 (en) * | 2011-08-29 | 2013-03-07 | Purdue Research Foundation | Continuous-flow solar ultraviolet disinfection system for drinking water |
| CN104298836A (en) * | 2014-11-06 | 2015-01-21 | 中国科学院合肥物质科学研究院 | Reactor core iterative design system based on Monte Carlo calculation |
| CN106773666A (en) * | 2016-11-11 | 2017-05-31 | 中国电力科学研究院 | A kind of model parameter acquisition methods for presurized water reactor primary Ioops system |
| WO2017173329A1 (en) * | 2016-04-01 | 2017-10-05 | Board Of Regents Of The Nevada System Of Higher Education, On Behalf Of The University Of Nevada, Reno | Systems and methods for enhancing energy extraction from geothermal wells |
| CN107808063A (en) * | 2017-11-22 | 2018-03-16 | 国网福建省电力有限公司 | A kind of HTGR emulation modelling method for Power System Analysis |
| CN108469744A (en) * | 2018-02-11 | 2018-08-31 | 东南大学 | A kind of method and its system for establishing nuclear power generating sets steam generator mechanism model |
| CN109830316A (en) * | 2019-02-22 | 2019-05-31 | 华北电力大学 | A kind of passive accident afterheat discharge system of sodium-cooled fast reactor intermediate loop |
| CN109903870A (en) * | 2019-03-15 | 2019-06-18 | 西安交通大学 | A kind of across dimension coupled simulation method of Nuclear Power System |
-
2019
- 2019-07-08 CN CN201910609570.3A patent/CN110531635B/en active Active
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2007025235A1 (en) * | 2005-08-26 | 2007-03-01 | Ppg Industries Ohio, Inc. | Method and apparatus for the production of ultrafine silica particles from solid silica powder and related coating compositions |
| KR20100120529A (en) * | 2009-05-06 | 2010-11-16 | 한국원자력연구원 | Device for heating a simulated core in sodium cooled fast reactor system |
| CN101620892A (en) * | 2009-07-30 | 2010-01-06 | 华北电力大学 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
| WO2013033144A2 (en) * | 2011-08-29 | 2013-03-07 | Purdue Research Foundation | Continuous-flow solar ultraviolet disinfection system for drinking water |
| CN104298836A (en) * | 2014-11-06 | 2015-01-21 | 中国科学院合肥物质科学研究院 | Reactor core iterative design system based on Monte Carlo calculation |
| WO2017173329A1 (en) * | 2016-04-01 | 2017-10-05 | Board Of Regents Of The Nevada System Of Higher Education, On Behalf Of The University Of Nevada, Reno | Systems and methods for enhancing energy extraction from geothermal wells |
| CN106773666A (en) * | 2016-11-11 | 2017-05-31 | 中国电力科学研究院 | A kind of model parameter acquisition methods for presurized water reactor primary Ioops system |
| CN107808063A (en) * | 2017-11-22 | 2018-03-16 | 国网福建省电力有限公司 | A kind of HTGR emulation modelling method for Power System Analysis |
| CN108469744A (en) * | 2018-02-11 | 2018-08-31 | 东南大学 | A kind of method and its system for establishing nuclear power generating sets steam generator mechanism model |
| CN109830316A (en) * | 2019-02-22 | 2019-05-31 | 华北电力大学 | A kind of passive accident afterheat discharge system of sodium-cooled fast reactor intermediate loop |
| CN109903870A (en) * | 2019-03-15 | 2019-06-18 | 西安交通大学 | A kind of across dimension coupled simulation method of Nuclear Power System |
Non-Patent Citations (5)
| Title |
|---|
| RASHMI NAWLAKHA,等: "Real Time Simulation and Analysis of Nuclear Core Temperature Monitoring System for PFBR", 《IEEE-INTERNATIONAL CONFERENCE ON RECENT TRENDS IN INFORMATION TECHNOLOGY》 * |
| YU YANG，等: "Dynamic Simulation Research on Primary Coolant System of Sodium Cooled Fast Reactor", 《ICONE20-POWER2012》 * |
| ZHANG ZHIGANG，等: "Research and Development on Simulator of Fast Reactor in China", 《INTERNATIONAL CONFERENCE ON FAST REACTORS AND RELATED FUEL CYCLES: NEXT GENERATION NUCLEAR SYSTEMS FOR SUSTAINABLE DEVELOPMENT (FR17)》 * |
| 刘勇，等: "大型钠冷快堆核电站蒸汽发生器仿真模型开发与分析", 《中国仪器仪表》 * |
| 高尚，等: "针对IVR-ERVC缩比试验台架的CFD模拟", 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会》 * |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112687408A (en) * | 2020-12-24 | 2021-04-20 | 中国原子能科学研究院 | Experimental model for sodium-cooled pool type fast reactor natural circulation experiment |
| CN113063816A (en) * | 2021-03-23 | 2021-07-02 | 华北电力大学 | Test bench for researching thermal oscillation of central column of fast reactor plug |
| CN113063816B (en) * | 2021-03-23 | 2022-07-26 | 华北电力大学 | Test bench for researching thermal oscillation of central column of fast reactor plug |
| CN113343597A (en) * | 2021-06-01 | 2021-09-03 | 潍柴动力股份有限公司 | Method and device for calculating virtual pressure behind throttle valve |
| CN113657049A (en) * | 2021-08-17 | 2021-11-16 | 哈尔滨工程大学 | Rapid simulation method for heat transfer and flow of main coolant system of pool type sodium-cooled fast reactor |
| CN113657049B (en) * | 2021-08-17 | 2023-06-16 | 哈尔滨工程大学 | Heat transfer and flow quick simulation method for pool type sodium-cooled fast reactor main coolant system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN110531635B (en) | 2020-10-23 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110531635A (en) | One kind being based on the fast reactor main pump circulation passage Modeling Calculation method of " virtual valve " | |
| CN110532586A (en) | A kind of the subregion decoupling modeling and overall coupling calculation of sodium-cooled fast reactor container | |
| CN106055850B (en) | A method of obtaining departure nucleate boiling type critical heat flux density | |
| CN111261232B (en) | Reactor primary loop coolant flow field, temperature field and stress field coupling calculation method | |
| CN108170924A (en) | One kind is for Steam Generators in NPP heat transfer pipe plug stream condition model method for building up | |
| CN109902433A (en) | Across the dimension coupling process of presurized water reactor passive containment residual heat removal system | |
| CN110020476A (en) | A kind of full three dimensional coupling model method for building up of the U-shaped pipe type steam generator of reactor | |
| CN109583104A (en) | A kind of nuclear reactor thermal-hydraulic simulation framework method based on modelica specification | |
| CN109190229B (en) | Method for simulating condensation reflux of steam in steel containment vessel of nuclear power plant | |
| CN111274748B (en) | Cross-dimension coupling calculation method for pool type sodium-cooled fast reactor passive waste heat removal system | |
| CN105893672B (en) | A kind of long and narrow river-like reservoir Life cycle Study on Temperature Field method | |
| Guo et al. | Accident safety analysis of flow blockage in an assembly in the JRR-3M research reactor using system code RELAP5 and CFD code FLUENT | |
| Park et al. | A multi-scale and multi-physics approach to main steam line break accidents using coupled MASTER/CUPID/MARS code | |
| CN106297918B (en) | A kind of output control device of overcritical electrical heating simulation transient state core heat release | |
| CN110223790A (en) | Stagnation pressure external container cooling test rack in a kind of fusant heap | |
| Jeong et al. | Coolant flow field in a real geometry of PWR downcomer and lower plenum | |
| Ye et al. | CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment | |
| Song et al. | RELAP5/MOD3. 4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000 | |
| Ha et al. | Evaluations of two-phase natural circulation flow induced in the reactor vessel annular gap under ERVC conditions | |
| Cheng et al. | Numerical investigation of channel for helium cooled China HCCB-TBM first wall by application enhance heat transfer method | |
| Böttcher et al. | Detail CFD simulation of the integrated reactor pressure vessel of SMART | |
| Yan | Coupled CFD-system-code simulation of a gas cooled reactor | |
| Zhao et al. | Numerical simulation of natural circulation characteristics under different DHX layout schemes in pool-type SFR during station blackout accident | |
| Carlucci et al. | The effects of symmetric/asymmetric boundary conditions on the flow of an internally heated fluid | |
| CN105761763A (en) | Backboard system structure of solid-state tritium production cladding experiment module |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |