CN115618620A - Pressurized water reactor grid node dividing method based on RELAP5 - Google Patents

Pressurized water reactor grid node dividing method based on RELAP5 Download PDF

Info

Publication number
CN115618620A
CN115618620A CN202211319903.7A CN202211319903A CN115618620A CN 115618620 A CN115618620 A CN 115618620A CN 202211319903 A CN202211319903 A CN 202211319903A CN 115618620 A CN115618620 A CN 115618620A
Authority
CN
China
Prior art keywords
control body
liquid phase
time
steam injection
pressurized water
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.)
Pending
Application number
CN202211319903.7A
Other languages
Chinese (zh)
Inventor
孙皖
李想
王辉
黄挺
孟召灿
连强
唐思邈
潘良明
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Chongqing University
State Power Investment Group Science and Technology Research Institute Co Ltd
Original Assignee
Chongqing University
State Power Investment Group Science and Technology Research Institute Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Chongqing University, State Power Investment Group Science and Technology Research Institute Co Ltd filed Critical Chongqing University
Priority to CN202211319903.7A priority Critical patent/CN115618620A/en
Publication of CN115618620A publication Critical patent/CN115618620A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F30/00Computer-aided design [CAD]
    • G06F30/20Design optimisation, verification or simulation

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Theoretical Computer Science (AREA)
  • Computer Hardware Design (AREA)
  • Evolutionary Computation (AREA)
  • Geometry (AREA)
  • General Engineering & Computer Science (AREA)
  • General Physics & Mathematics (AREA)
  • Management, Administration, Business Operations System, And Electronic Commerce (AREA)

Abstract

The invention discloses a pressurized water reactor grid node dividing method based on RELAP5, which comprises the following steps of S1: firstly, carrying out first data collection on a modeling object, and then carrying out node division on the modeling object to obtain node information, wherein the node information comprises pipe fitting labels and control body numbers; s2: importing the node information obtained in the step S1 into an Input card of RELAP5 to form control body information; s3: adding the control body information in the Input card obtained in the step S2 into a RELAP5 system program for running to obtain the change data of the control body parameters along with the time; s4: and writing the change data of the control body parameters with time into a Result card for displaying. The method can conveniently and quickly obtain the required node division result under the conditions of obtaining the geometric parameters, the operating parameters and the like of the modeling object, and improve the node division efficiency.

Description

Pressurized water reactor grid node dividing method based on RELAP5
Technical Field
The invention relates to the technical field of nuclear power, in particular to a pressurized water reactor grid node dividing method based on RELAP 5.
Background
The RELAP Program is called Reactor Excursion and Leak Analysis Program, is one of large programs with perfect physical models at present, is also the basis of safety Analysis of a plurality of commercial water-cooled Reactor nuclear power plants in the world, and is widely applied to the aspects of design, safety inspection and the like of the nuclear power plants. The program can be used for simulating the water loss accident of the water-cooled reactor of the nuclear power station, the rupture accident of a main steam pipeline, the rupture accident of a heat transfer pipeline of a steam generator, the loss accident of main water supply and the like. The FORTRAN language is used as bottom-layer code, and then the code is divided into three primary component modules and a transient steady state calculation module according to functions. For a complete example, the node partitioning scheme is determined first, because different node partitions will have a certain influence on the computation result of the RELAP 5. For the descending section part of the pressurized water reactor, node division in the prior art generally generates huge amounts of node information data, the manual and autonomous input process is very complicated and inefficient, and the overall working efficiency is reduced.
Disclosure of Invention
Aiming at the problem that the efficiency of dividing the nodes of the descending section of the pressurized water reactor is low in the prior art, the invention provides a pressurized water reactor grid node dividing method based on RELAP5, the peripheral nodes of the descending section are refined, and a large number of nodes are automatically divided by using commercial mathematical programming software MATLAB, so that the node dividing efficiency is improved.
In order to achieve the purpose, the invention provides the following technical scheme:
the pressurized water reactor grid node dividing method based on RELAP5 specifically comprises the following steps:
s1: firstly, carrying out first data collection on a modeling object, and then carrying out node division on the modeling object to obtain node information, wherein the node information comprises pipe part labels and control body numbers;
s2: importing the node information obtained in the step S1 into an Input card of RELAP5 to form control body information;
s3: adding the control body information in the Input card obtained in the step S2 into a RELAP5 system program for running to obtain the change data of the control body parameters along with the time;
s4: and writing the change data of the control body parameters with time into a Result card for displaying.
Preferably, in S1, the first data includes geometric parameters, such as diameter and length of the cold pipe section, inner and outer diameters and height of the descending section, and thermal hydraulic parameters, such as temperature and pressure.
Preferably, in S1, the node division method includes:
the modeling object comprises a first part, a second part, a third part and a fourth part which are sequentially connected, namely, the first part is communicated and connected with the third part through the second part, and the third part is communicated with the fourth part;
the first part comprises n first pipe fittings connected in parallel, the second part also comprises n second pipe fittings connected in parallel, and the third part also comprises n third pipe fittings connected in parallel; the first pipe fitting is communicated with the third pipe fitting through the corresponding second pipe fitting, and the third pipe fitting is communicated with the fourth part; and adjacent pipe fittings in each part are connected by adopting a plurality of connecting pipes to form an annular channel.
Preferably, a water injection circuit is also included:
the output end of the time control body TDV is connected with the input end of the time connecting pipe TDJ, the output end of the time connecting pipe TDJ is connected with the input end of the cold pipe section, and the output end of the cold pipe section is connected with the second pipe fitting of the second part; the time control body TDV gives water injection boundary conditions, the time connecting pipe TDJ gives the injection cooling water flow of the cold pipe section, and the cold pipe section is a circulating pipeline.
Preferably, the number of water injection circuits is 3, arranged at 45 ° -135 °.
Preferably, the system further comprises a simulation destruction loop, wherein the destruction loop comprises a trigger valve, a destruction control body and a destruction time control body:
the second component is connected with one end of a trigger valve through a cold pipe section, the other end of the trigger valve is connected with one end of a damage control body, and the other end of the damage control body is connected with a damage time control body; the trigger valve is used for being opened at the time of 0 so as to simulate a double-end shear fracture and break accident; the damage control body is used for simulating a containment simulator; in the embodiment, the bad time control body provides a backpressure boundary condition for the bad time control body.
Preferably, still include and annotate the vapour return circuit, annotate the vapour return circuit and include annotate vapour time control body, annotate vapour control body:
the output end of the steam injection time control body is connected with the input end of the steam injection control body, and the output end of the steam injection control body is connected with a steam injection port of the fourth part through a cold pipe section; the steam injection time control body is used for providing steam injection boundary conditions; and the steam injection control body is used for simulating the cross section of the reactor core channel.
Preferably, in S3, the calculation formula of the time-dependent variation data of the control body parameter is as follows:
continuity equation:
Figure RE-GDA0003988197810000031
in the formula (1), α k Is the gas-liquid phase void fraction, ρ k Is the gas-liquid phase density, v k Gas-liquid phase velocity, A is cross-sectional area; g represents a gas phase, f represents a liquid phase, and Γ represents a mass transfer term;
conservation of gas phase momentum:
Figure RE-GDA0003988197810000032
conservation of liquid phase momentum:
Figure RE-GDA0003988197810000033
in the formula (2), α g 、ρ g 、v g 、P、x、B x 、Γ g 、v gI 、FIG、v f 、C、ρ m T and FWG respectively represent gas phase void fraction, gas phase density, gas phase velocity, pressure, spacing distance, force in the x coordinate direction, volume mass exchange rate, gas phase interface velocity, gas phase interphase resistance coefficient, liquid phase velocity, virtual mass coefficient, mixing density, time, and gas phase wall resistance coefficient;
in the formula (3), α f 、ρ f 、v f 、v fI FIF and FWF respectively represent the void fraction of liquid phase, liquid phase density, liquid phase speed, liquid phase interface speed, liquid phase interphase resistance coefficient and liquid phase wall resistance coefficient.
In summary, due to the adoption of the technical scheme, compared with the prior art, the invention at least has the following beneficial effects:
1) The required node division result can be conveniently and quickly obtained under the conditions of obtaining geometric parameters, operation parameters and the like of the modeling object;
2) According to the method, the required descending segment nodes are automatically divided by programming through MATLAB software according to the requirements of calculation and analysis, and people who know the software with certain knowledge can realize the method, so that the method is flexible and convenient;
3) The model is independent, the method is strong in universality, and the method can be suitable for calculation analysis results of different node division schemes.
Description of the drawings:
fig. 1 is a flow chart of a pressurized water reactor grid node division method based on RELAP5 according to an exemplary embodiment of the invention.
Fig. 2 is a schematic diagram of node partitioning according to an exemplary embodiment of the present invention.
Detailed Description
The present invention will be described in further detail with reference to examples and embodiments. It should be understood that the scope of the above-described subject matter of the present invention is not limited to the following examples, and any technique realized based on the contents of the present invention is within the scope of the present invention.
In the description of the present invention, it is to be understood that the terms "longitudinal", "lateral", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", etc. indicate orientations or positional relationships based on those shown in the drawings, and are merely for convenience of description and simplicity of description, but do not indicate or imply that the device or element referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and thus, are not to be construed as limiting the present invention.
As shown in fig. 1, the invention provides a pressurized water reactor grid node partitioning method based on RELAP5, taking modeling of a descending section part in a Test device of a typical pressurized water reactor Upper chamber Test bench UPTF (Upper Plenum Test Facility) Test 6 as an example, further detailed description is made on the invention, and specifically includes the following steps:
s1: firstly, first data collection is carried out on a modeling object (namely a descending section part of a pressurized water reactor), the first data comprises the diameter and the length of a geometric parameter cold pipe section, the inner and outer diameters and the height of the descending section, the temperature and the pressure of a thermal hydraulic parameter and the like, then, a whole node dividing and constructing frame is carried out on the modeling object, a node map is designed, and node information is obtained and comprises pipe fitting labels, the number of control bodies, the hydraulic diameter and the like.
As shown in fig. 2, the modeling object includes a first portion, a second portion, a third portion and a fourth portion, which are connected in sequence, that is, the first portion is communicated with the third portion through the second portion, and the third portion is communicated with the fourth portion.
The first part comprises n first pipes connected in parallel, which can be marked P2XX; the second part likewise comprises n second tubes connected in parallel, which can be designated B1XX; the third section likewise comprises n parallel third tubes, which can be designated P3XX; the first pipe fitting is communicated with a third pipe fitting through a corresponding second pipe fitting, and the third pipe fitting is communicated with the fourth part; and adjacent pipe fittings in each part are connected by adopting a plurality of connecting pipes to form an annular channel.
Still include the water injection return circuit:
the output end of the time control body TDV is connected with the input end of the time connecting pipe TDJ, the output end of the time connecting pipe TDJ is connected with the input end of the cold pipe section, and the output end of the cold pipe section is connected with the second pipe fitting of the second part; the TDV of the time control body gives water injection boundary conditions, the TDJ of the time connecting pipe gives injection cooling water flow of a cold pipe section of the complete loop, and the cold pipe section is a circulating pipeline.
In this embodiment, the number of water injection circuits is preferably 3, arranged in an arrangement of 45 ° to 135 ° according to the experiment.
Still including the simulation and destroy the loop, destroy the loop and include trigger valve, destroy the control body and destroy the time control body:
the second part is connected with one end of the trigger valve through the cold pipe section, the other end of the trigger valve is connected with one end of the destruction control body, and the other end of the destruction control body is connected with the destruction time control body. The trigger valve is used for being opened at the time of 0 so as to simulate a double-end shear fracture and break accident; the damage control body is used for simulating a containment simulator; in the embodiment, the bad time control body provides a backpressure boundary condition for the bad time control body.
In this embodiment, still include the steam injection return circuit, the steam injection return circuit includes the steam injection time control body, annotates the steam control body:
the output end of the steam injection time control body is connected with the input end of the steam injection control body, and the output end of the steam injection control body is connected with the steam injection port of the fourth part through the cold pipe section. And the steam injection time control body is used for providing steam injection boundary conditions and simulating the cross section of a reactor core channel.
In this embodiment, taking circumferential 16 nodes as an example:
the first part comprises 16 first pipes connected in parallel, which are respectively marked as P211-P226; the second part comprises 16 second pipes connected in parallel, and the second pipes are respectively marked as B111-B126; the third part comprises 16 third pipes connected in parallel, and the third pipes are respectively marked as P311-P326; the fourth part is a simulated lower chamber, which may be labeled as P411. The first pipe fitting is communicated with the third pipe fitting through the corresponding second pipe fitting, for example, P211 is communicated with P311 through B111, P212 is communicated with P312 through B112, P226 is communicated with P326 through B126, and P311-P326 are communicated with P411.
The water injection loop comprises a first water injection loop, a second water injection loop and a third water injection loop which are arranged in a 45-135 degree mode. The first water injection loop comprises a first TDV, a first TDJ and a first Valve which are connected in sequence, and the first Valve is connected with the B111; the second water injection loop comprises a second TDV, a second TDJ and a second Valve which are connected in sequence, and the second Valve is connected with the B117; the third water injection loop comprises a third TDV, a third TDJ and a third Valve which are connected in sequence, and the third Valve is connected with B119.
The damage loop comprises a trigger valve, a damage control body and a damage time control body:
the second component B125 is connected with one end of a trigger valve through a cold pipe section, the other end of the trigger valve is connected with one end of a destruction control body, and the other end of the destruction control body is connected with a destruction time control body.
In this embodiment, a multi-tap part MTPLJUN is used between adjacent keys of each part to simulate uneven flow. While adjacent parts are connected using the multi-pipe segment MTPLJUN. For example, the first pipe P211 of the first section is connected to the second pipe B111 of the second section by a multi-joint part MTPLJUN, and B111 is connected to the third pipe P311 of the third section by a multi-joint part MTPLJUN.
However, the above node division will involve a large amount of node data, if manual programming input is adopted, the time consumption is long and errors are easy to occur, so the MATLAB programming software is adopted to realize automatic calculation and programming of the node division of the descending segment, and the specific steps are as follows:
the pipe fitting number NNN, the number NV of the control bodies, the length LX along the x-axis direction of the control bodies, the flow cross-section area AreaX along the x-axis direction of the control bodies, the vertical azimuth angle Vrt _ ang, the pipe wall friction coefficient WallX _ rough along the x-axis direction, the hydraulic diameter HydiaX, the flow cross-section area AreaY along the y-axis direction, the hydraulic diameter HydiaY along the y-axis direction and other parameters are specifically input into a compiled MATLAB program, and required node information is solved.
For example: cardNo = [ num2str (NNN), '0000' ];
CardNo=str2num(CardNo);
Name2=[Name num2str(NNN)];
fprintf (fid, '% i% s \ n', cardNo, name2, 'pipe'), where NNN is the pipe designation.
S2: importing the node information obtained in the step S1 into an Input card of RELAP5-MOD3.3, and further compiling to form a complete Input card to form control body information (including specific geometric parameters, hydraulic parameters and the like); namely, after a series of input information such as pipe fitting labels, the number of control bodies, the hydraulic diameter and the like is given, various types of control body information can be output, for example: and outputting the information of the single connection pipe.
CardNo=[num2str(NNN),'0000'];
CardNo=str2num(CardNo);
Name2=[Name num2str(NNN)];
fprintf(fid,'%i%s%s\n',CardNo,Name2,'sngljun');
CardNo=[num2str(NNN),'0101'];
CardNo=str2num(CardNo);
fprintf(fid,'%i%i%i%.4f%2.1f%2.1f%s\n',CardNo,C omp_From,Comp_To,Area,F_loss,R_loss,Flags);
CardNo=[num2str(NNN),'0110'];
CardNo=str2num(CardNo);
fprintf(fid,'%i%f%.2f%.4f%.4f\n',CardNo,Hydia,Beta,c,m); CardNo=[num2str(NNN),'0201'];
CardNo=str2num(CardNo);
fprintf(fid,'%i%i%2.1f%2.1f%2.1f\n',CardNo,1,0.0,0.0,0.0)。
S3: adding the Input card obtained in the step S2 into a RELAP5 system program for operation, namely calculating a corresponding continuity equation, a gas phase momentum conservation equation and a liquid phase momentum conservation equation according to control body information, dispersing the equations by using semi-implicit or implicit method (replacing a differential equation set by a partial implicit finite difference equation set, an implicit term can be expressed as a linear dependent variable at a new moment, and the equations can be simplified into a single differential equation of each fluid control volume or grid unit), and solving the control body according to the earlier Input operation parameters to obtain the change data of the control body parameters along with time, including the change data of pressure, flow rate, flow and the like along with time; the specific corresponding formula can be queried from the RELAP5 manual; namely, the control body information is input into the existing RELAP5 system program, and the change data of the control body parameters along with time can be obtained.
Continuity equation:
Figure RE-GDA0003988197810000091
in the formula (1), α k Is the void fraction of the gas-liquid phase, p k Is gas-liquid phase density, v k Gas-liquid phase velocity, A is cross-sectional area; g represents a gas phase, f represents a liquid phase, and Γ represents a mass transfer term.
Conservation of gas phase momentum:
Figure RE-GDA0003988197810000092
conservation of liquid phase momentum:
Figure RE-GDA0003988197810000093
in the formula (2), α g 、ρ g 、v g 、P、x、B x 、Γ g 、v gI 、FIG、v f 、C、ρ m T and FWG respectively represent gas phase void fraction, gas phase density, gas phase velocity, pressure, spacing distance, force in the x coordinate direction, volume mass exchange rate, gas phase interface velocity, gas phase interphase resistance coefficient, liquid phase velocity, virtual mass coefficient, mixing density, time and gas phase wall resistance coefficient.
In the formula (3), α f 、ρ f 、v f 、v fI FIF and FWF respectively represent the void fraction of liquid phase, liquid phase density, liquid phase speed, liquid phase interface speed, liquid phase interphase resistance coefficient and liquid phase wall resistance coefficient.
S4: and writing the data of the parameters of the control body along with the change of time into a Result card for the analysis of a subsequent control body, and searching and modifying through the Output card to debug the program.
In the embodiment, the change data of the parameters of the output control body along with time can be calculated only by giving the pipe fitting labels needing to be set, relevant geometric parameters, thermal hydraulic parameters and the like, so that the problem of low node division efficiency is solved.
It will be understood by those of ordinary skill in the art that the foregoing embodiments are specific examples for carrying out the invention, and that various changes in form and details may be made therein without departing from the spirit and scope of the invention in practice.

Claims (8)

1. The pressurized water reactor grid node dividing method based on RELAP5 is characterized by comprising the following steps:
s1: firstly, carrying out first data collection on a modeling object, and then carrying out node division on the modeling object to obtain node information, wherein the node information comprises pipe fitting labels and control body numbers;
s2: importing the node information obtained in the step S1 into an Input card of RELAP5 to form control body information;
s3: adding the control body information in the Input card obtained in the step S2 into a RELAP5 system program for running to obtain the change data of the control body parameters along with the time;
s4: and writing the change data of the control body parameters with time into a Result card for displaying.
2. The RELAP 5-based pressurized water reactor grid node division method according to claim 1, wherein in S1, the first data comprise geometric parameters including diameter and length of a cold pipe section, inner and outer diameters and height of a descending section, and thermal hydraulic parameters including temperature and pressure.
3. The RELAP 5-based pressurized water reactor grid node division method according to claim 1, wherein in S1, the node division method comprises:
the modeling object comprises a first part, a second part, a third part and a fourth part which are sequentially connected, namely, the first part is communicated and connected with the third part through the second part, and the third part is communicated with the fourth part;
the first part comprises n first pipe fittings connected in parallel, the second part also comprises n second pipe fittings connected in parallel, and the third part also comprises n third pipe fittings connected in parallel; the first pipe fitting is communicated with the third pipe fitting through the corresponding second pipe fitting, and the third pipe fitting is communicated with the fourth part; and adjacent pipe fittings in each part are connected by adopting a plurality of connecting pipes to form an annular channel.
4. The RELAP 5-based pressurized water reactor grid node division method as defined in claim 3, further comprising a water injection circuit:
the output end of the time control body TDV is connected with the input end of the time connecting pipe TDJ, the output end of the time connecting pipe TDJ is connected with the input end of the cold pipe section, and the output end of the cold pipe section is connected with the second pipe fitting of the second part; the time control body TDV gives a water injection boundary condition, the time connecting pipe TDJ gives an injection cooling water flow of the cold pipe section, and the cold pipe section is a circulating pipeline.
5. The RELAP 5-based pressurized water reactor grid node division method as claimed in claim 4, wherein the number of the water injection loops is 3 and the water injection loops are arranged at 45-135 degrees.
6. The RELAP 5-based pressurized water reactor grid node partitioning method of claim 3, further comprising simulating a destruction loop, the destruction loop including a trigger valve, a destruction control, and a destruction time control:
the second component is connected with one end of a trigger valve through a cold pipe section, the other end of the trigger valve is connected with one end of a damage control body, and the other end of the damage control body is connected with a damage time control body; the trigger valve is used for being opened at the time of 0 so as to simulate a double-end shear fracture break accident; the damage control body is used for simulating a containment simulator; in the embodiment, the bad time control body provides a backpressure boundary condition for the bad time control body.
7. The RELAP 5-based pressurized water reactor grid node division method according to claim 3, further comprising a steam injection loop, wherein the steam injection loop comprises a steam injection time control body and a steam injection control body:
the output end of the steam injection time control body is connected with the input end of the steam injection control body, and the output end of the steam injection control body is connected with a steam injection port of the fourth part through a cold pipe section; the steam injection time control body is used for providing steam injection boundary conditions; and the steam injection control body is used for simulating the cross section of the reactor core channel.
8. The RELAP 5-based pressurized water reactor grid node division method according to claim 3, wherein in S3, the calculation formula of the time-dependent change data of the control volume parameters is as follows:
continuity equation:
Figure RE-FDA0003988197800000021
in the formula (1), α k Is the void fraction of the gas-liquid phase, p k Is gas-liquid phase density, v k Gas-liquid phase velocity, A is cross-sectional area; g represents a gas phase, f represents a liquid phase, and Γ represents a mass transfer term;
conservation of gas phase momentum:
Figure RE-FDA0003988197800000031
conservation of liquid phase momentum:
Figure RE-FDA0003988197800000032
in the formula (2), α g 、ρ g 、v g 、P、x、B x 、Γ g 、v gI 、FIG、v f 、C、ρ m T and FWG respectively represent gas phase void fraction, gas phase density, gas phase velocity, pressure, spacing distance, force in the x coordinate direction, volume mass exchange rate, gas phase interface velocity, gas phase interphase resistance coefficient, liquid phase velocity, virtual mass coefficient, mixing density, time and gas phase wall surface resistance coefficient;
in the formula (3), α f 、ρ f 、v f 、v fI FIF and FWF respectively represent the void fraction of liquid phase, liquid phase density, liquid phase speed, liquid phase interface speed, liquid phase interphase resistance coefficient and liquid phase wall resistance coefficient.
CN202211319903.7A 2022-10-26 2022-10-26 Pressurized water reactor grid node dividing method based on RELAP5 Pending CN115618620A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202211319903.7A CN115618620A (en) 2022-10-26 2022-10-26 Pressurized water reactor grid node dividing method based on RELAP5

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202211319903.7A CN115618620A (en) 2022-10-26 2022-10-26 Pressurized water reactor grid node dividing method based on RELAP5

Publications (1)

Publication Number Publication Date
CN115618620A true CN115618620A (en) 2023-01-17

Family

ID=84864013

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202211319903.7A Pending CN115618620A (en) 2022-10-26 2022-10-26 Pressurized water reactor grid node dividing method based on RELAP5

Country Status (1)

Country Link
CN (1) CN115618620A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115531934A (en) * 2022-10-26 2022-12-30 重庆大学 Sludge discharge control method for sedimentation tank

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115531934A (en) * 2022-10-26 2022-12-30 重庆大学 Sludge discharge control method for sedimentation tank

Similar Documents

Publication Publication Date Title
Spalding GENMIX: A general computer program for two-dimensional parabolic phenomena
CN109903870B (en) Cross-dimension coupling simulation method for nuclear power system
Angeli et al. Overview of the TrioCFD code: Main features, VetV procedures and typical applications to nuclear engineering
CN107357961A (en) Spacecraft propulsion system dynamic analysing method based on Modelica models
CN111144054B (en) Modeling method for natural circulation characteristic of villiaumite cooling high-temperature reactor passive waste heat discharge system
CN115618620A (en) Pressurized water reactor grid node dividing method based on RELAP5
Adelaja et al. Computer aided analysis of thermal and mechanical design of shell and tube heat exchangers
Hirsch et al. An efficient numerical solution method for detailed modelling of large 5th generation district heating and cooling networks
CN109977578A (en) Large-scale board-like heat sink CFD structural optimization method
CN114266171A (en) Method for calculating total coupling conjugate heat transfer of U-shaped tube steam generator
CN108763741A (en) A kind of hydraulic hose fluid structurecoupling Numerical Predicting Method
Yoon et al. A multiscale and multiphysics PWR safety analysis at a subchannel scale
CN114491864A (en) Nuclear power pipe network model preprocessing method with parameterization and reconfigurable characteristics
Zanino et al. CFD modeling of ITER cable‐in‐conduit superconductors. Part I: Friction in the central channel
CN112949120B (en) Matlab/Simulink-based method for realizing coupling calculation of tritium transport models with different dimensions
CN112182905B (en) Heat supply pipe network simulation method and device for comprehensive energy system
CN103971774A (en) Method and system for storing, displaying and playing back design, operation and safety analysis data of nuclear power station
Vallone et al. Numerical assessment of the thermal-hydraulic performances of the ITER blanket cooling system
Boulos et al. On the solvability of water distribution networks with unknown pipe characteristics
Zhang CFD simulations and thermal design for application to compressed air energy storage
CN110728030A (en) Method for simulating coupling of two sides of steam and water based on numerical value of surface condenser
Cheng Strategies for developing subchannel capability in an advanced system thermalhydraulic code: a literature review
Habeck Mixed-integer optimization with ordinary differential equations for gas networks
Pan et al. High-order gas-kinetic scheme in curvilinear coordinates for the Euler and Navier-Stokes solutions
Yildiz et al. Large eddy simulation of 5-tube bundle helical coil steam generator test section

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