CN112052998B - Spent fuel pool boiling time real-time prediction system and method - Google Patents
Spent fuel pool boiling time real-time prediction system and method Download PDFInfo
- Publication number
- CN112052998B CN112052998B CN202010936983.5A CN202010936983A CN112052998B CN 112052998 B CN112052998 B CN 112052998B CN 202010936983 A CN202010936983 A CN 202010936983A CN 112052998 B CN112052998 B CN 112052998B
- Authority
- CN
- China
- Prior art keywords
- time
- spent fuel
- pool
- fuel pool
- temperature
- 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.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/04—Forecasting or optimisation specially adapted for administrative or management purposes, e.g. linear programming or "cutting stock problem"
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q50/00—Systems or methods specially adapted for specific business sectors, e.g. utilities or tourism
- G06Q50/06—Electricity, gas or water supply
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
-
- 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
- Engineering & Computer Science (AREA)
- Business, Economics & Management (AREA)
- Physics & Mathematics (AREA)
- Economics (AREA)
- Human Resources & Organizations (AREA)
- Strategic Management (AREA)
- Health & Medical Sciences (AREA)
- Theoretical Computer Science (AREA)
- General Physics & Mathematics (AREA)
- Marketing (AREA)
- General Business, Economics & Management (AREA)
- Tourism & Hospitality (AREA)
- General Health & Medical Sciences (AREA)
- Primary Health Care (AREA)
- Water Supply & Treatment (AREA)
- Public Health (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Development Economics (AREA)
- Game Theory and Decision Science (AREA)
- Entrepreneurship & Innovation (AREA)
- Operations Research (AREA)
- Quality & Reliability (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to the technical field of spent fuel pool boiling time prediction, in particular to a system and a method for predicting spent fuel pool boiling time in real time. The system for predicting the boiling time of the spent fuel pool in real time comprises a spent fuel decay heat calculation module, a data processing module and a data processing module, wherein the spent fuel decay heat calculation module is used for calculating decay heat of a fuel assembly through a spent fuel decay heat calculation model and by combining historical operation data of the fuel assembly; the production real-time data acquisition module is used for acquiring production real-time data related to the temperature change of the spent fuel pool; and the pool heat exchange calculation module is used for obtaining parameters through a pool heat exchange calculation model and combining the decay heat of the fuel assembly and the production real-time data to calculate and obtain the function relation between the water temperature of the spent fuel pool and the time. According to the method and the device, the boiling time of the spent fuel pool can be predicted in real time, relevant parameters of unit spent fuel pool temperature calculation are obtained in real time under accident conditions, and the change of the spent fuel pool temperature along with the time, the boiling time of the spent fuel pool and the exposure time of the components are fed back in real time.
Description
Technical Field
The invention relates to the technical field of spent fuel pool boiling time prediction, in particular to a system and a method for predicting spent fuel pool boiling time in real time.
Background
The spent fuel pool is a facility used for storing spent fuel by a wet method in a nuclear power plant. The spent fuel, which has a large residual decay power after being discharged from the reactor, needs to be stored in a spent fuel pool, continuously cooled by means of a cooling system associated with the nuclear power plant, and takes away decay heat. When the spent fuel pool is cooled and fails, the decay heat of the spent fuel continuously heats the pool water to boil and evaporate, the water level of the spent fuel pool is reduced, the spent fuel is gradually exposed in a steam environment, and finally cladding damage and redistribution of fuel pellets are caused, so that the risks of critical safety and radioactive release are brought. In 2011, the number 4 unit of the first nuclear power plant in the fukushima causes ac power loss due to earthquakes and tsunamis, and the liquid level of a spent fuel pool is lowered due to the loss of a cooling function and a water replenishing function of the spent fuel pool, so that explosion, fire and partial radioactive substances are finally caused to leak.
In order to improve the emergency ability of each nuclear power plant under the accident condition of the spent fuel pool, the spent fuel pool provides decision reference under the accident condition, so that the time required for the water temperature in the spent fuel pool to reach the boiling point is calculated when the event that the spent fuel pool loses cooling or coolant capacity is lost needs to be predicted, and the emergency degree of corrective action is determined.
The boiling time of a spent fuel pool is calculated by a domestic nuclear power plant by adopting the following method:
when the refueling design work is carried out, a refueling design party synchronously compiles a spent fuel pool decay heat and temperature rise assessment report after unloading, decay heat calculation is carried out according to the state of a spent fuel pool fuel storage assembly after refueling, and a related report is provided for a nuclear power owner after the temperature rise rate after cooling loss is calculated.
The method has the following defects:
1. temperature rise data of a spent fuel pool provided by a nuclear power design institute is generally completed in 1 cycle before shutdown, and a power operation trend is calculated from design fuel consumption full power operation to shutdown. The actual operation condition of the power plant is complex, and planned power changes and trends such as peak shaving, regulation and stopping, extended operation and the like may exist. Therefore, the data predicted by the method for predicting the decay heat and the temperature rise of the spent fuel pool by the current design institute have the problems of insufficient precision, poor flexibility and the like.
2. Under the accident condition, the calculation of the boiling time of the spent fuel pool when the spent fuel pool is cooled plays an important role in the key decision of the power plant. According to the temperature rise rate given in the report, the boiling time of the spent fuel pool is calculated manually by combining various actually measured data of the on-site spent fuel pool, and the method has the defects of poor timeliness, large manual calculation amount and the like. Under the accident condition, all work minutes and seconds are necessary, and the boiling time of the spent fuel pool is manually calculated to provide reference for operation decision in time. The boiling time of the spent fuel pool calculated by the traditional method is long, the efficiency is low, and the real-time prediction of the boiling time of the spent fuel pool cannot be realized.
3. Under the accident condition, various parameters of the spent fuel pool are continuously changed, the boiling temperature of the spent fuel pool is manually calculated according to the manually read data, the calculation result possibly deviates from the current state, and the support cannot be accurately provided for operators.
Disclosure of Invention
The invention provides a system and a method for predicting the boiling time of a fuel water pool in real time aiming at the problems in the prior art, and the system and the method can acquire the boiling time of the spent fuel water pool in real time by constructing a spent fuel decay heat calculation model and a water pool heat exchange calculation model and providing input parameters required by temperature rise analysis in real time.
The technical scheme adopted by the invention for solving the technical problems is as follows: a spent fuel pool boiling time real-time prediction system comprises
The spent fuel decay heat calculation module is used for calculating decay heat of the fuel assembly through a spent fuel decay heat calculation model and by combining historical operation data of the fuel assembly;
the production real-time data acquisition module is used for acquiring production real-time data related to temperature change of the spent fuel pool;
the pool heat exchange calculation module is used for obtaining parameters through a pool heat exchange calculation model and combining decay heat and production real-time data of the fuel assembly to calculate and obtain a function relation between the water temperature of the spent fuel pool and time;
and the spent fuel pool boiling time prediction module is used for predicting the spent fuel pool boiling time in real time according to the function relation between the water temperature of the spent fuel pool and the time.
The system can realize real-time heat exchange calculation of the spent fuel pool through the real-time boiling time prediction system of the spent fuel pool. And (3) accurately calculating decay heat data of the fuel assembly by using a burn-up equation and combining actual operation power and a burn-up history of the power plant. Production data related to temperature rise of the spent fuel pool in the power plant is transmitted to the system, so that the temperature rise and boiling time of the spent fuel pool and the exposure time of the fuel assembly can be displayed in real time, the boiling time of the spent fuel pool is accurately monitored in real time, and reference is provided for decision making under accidents.
Preferably, the calculation model of the decay heat of the spent fuel is a fuel consumption equation.
Preferably, the historical operating data includes operating historical power, power change time burnup, load handling time, start-up time, critical time, trip time, and fuel assembly trip burnup.
Preferably, the pool heat exchange calculation model is a dual-system coupling model, and the dual-system coupling model is a coupling ordinary differential equation set of the spent fuel body system and the spent fuel pool cooling water system.
Preferably, the production real-time data comprises the liquid level of the spent fuel pool, the temperature of the spent fuel pool, the flow of a cooling water system of the spent fuel pool, the inlet temperature of the cooling water system of the spent fuel pool, the flow and the temperature of a waste heat discharge system, the flow and the temperature of a cooling water system of equipment, the flow and the temperature of cooling water of a passive containment and the flow and the temperature of fire-fighting water.
Preferably, the boiling time of the spent fuel pool comprises the boiling time of pool water under the optimal working condition, the exposure time of a pipe seat on an assembly under the optimal working condition, the boiling time of pool water under the limiting working condition and the exposure time of a pipe seat on an assembly under the limiting working condition.
A spent fuel pool boiling time real-time prediction method comprises the following steps
S01, calculating decay heat of the fuel assembly through a spent fuel decay heat calculation model and by combining historical operation data of the fuel assembly;
s02, acquiring production real-time data related to temperature change of the spent fuel pool;
s03, obtaining a function relation between the water temperature and the time of the spent fuel pool through a pool heat exchange calculation model and parameter calculation by combining decay heat of the fuel assembly and production real-time data;
and S04, predicting the boiling time of the spent fuel pool in real time according to the function relation of the water temperature of the spent fuel pool and the time.
According to the method, a spent fuel decay heat calculation and pool heat exchange calculation model is established, and input parameters required by temperature rise analysis are provided in real time, so that the boiling time of the spent fuel pool is monitored in real time. Based on the method, the content of the temperature rise calculation of the spent fuel pool of the nuclear power plant at present is realized, and nuclear power plant personnel can analyze the heat exchange capacity of the spent fuel pool in real time, so that the method has obvious improvement compared with the traditional calculation mode.
Preferably, in the step S03, the water pool heat exchange calculation model is solved by a 4-order lunge-kuta method.
Preferably, the physical property parameter of water in S03 is determined by the following steps
S31, determining the constant-pressure specific heat capacity: through statistical analysis, the variance value of the constant-pressure specific heat capacity of water in the temperature interval is smaller, and the variance value is regarded as a constant when the water pool heat exchange calculation model is solved;
s32 determines the specific enthalpy: calculating by using a linear regression equation, wherein the inlet temperature of each path of cooling water of the spent fuel pool is measured by a production real-time data acquisition module in real time, and the temperature corresponding to the specific enthalpy of an outlet is the temperature of the pool water;
s33 determines the density: the density of water is a function of temperature, the coefficient of linear correlation is higher in a given temperature interval of 0-100 ℃, and the density of water is calculated by using the linear regression equation thereof.
Preferably, the convective heat transfer model of the fuel assembly and the cooling water in S03 is large-space convective heat transfer of a stationary cylinder, and the gladaff number is used to calculate the total heat transfer coefficient.
Advantageous effects
The method can calculate the temperature of the spent fuel pool in real time and predict the boiling time of the spent fuel pool, acquire relevant parameters calculated by the temperature of the spent fuel pool of the unit in real time under the accident condition, and feed back the change of the temperature of the spent fuel pool along with the time, the boiling time of the spent fuel pool and the exposure time of the components in real time, so that the method can efficiently and accurately provide reference for decision making; the application greatly saves the labor cost, improves the capability of on-site calculation and analysis of nuclear power plant personnel under accident conditions, improves the level of the nuclear power plant personnel in the aspect of safety analysis of the spent fuel pool, and ensures the heat exchange safety of the spent fuel pool.
Drawings
FIG. 1 is a schematic diagram of a hardware structure of a spent fuel pool heat exchange model according to the present application;
fig. 2 is a calculation flow chart of the real-time heat exchange of the present application.
Detailed Description
The technical scheme of the invention is further explained by the specific implementation mode in combination with the attached drawings.
The utility model provides a real-time prediction system of boiling time of fuel pool, including be used for through the spent fuel decay heat calculation module of fuel assembly decay heat with the historical operating data calculation of fuel assembly, be used for acquireing the production real-time data acquisition module of the relevant production real-time data of spent fuel pool temperature change, be used for through pond heat transfer calculation module and combine fuel assembly decay heat and production real-time data acquisition parameter to calculate the pond heat transfer calculation module of the functional relation of spent fuel pool water temperature and time, be used for according to the spent fuel pool water temperature and the real-time prediction spent fuel pool boiling time prediction module of boiling time of time spent fuel pool.
The spent fuel decay heat calculation model is a fuel consumption equation. The pool heat exchange calculation model is a dual-system coupling model (the hardware structure of which is shown in fig. 1), and the dual-system coupling model is a coupling ordinary differential equation set of a spent fuel body system and a spent fuel pool cooling water system. The historical operating data includes operating historical power, power change time burnup, load and unload time, start-up time, critical time, trip time, and fuel assembly trip burnup. The decay heat data used in the spent fuel pool boiling time real-time prediction system is decay heat data calculated according to power history simulation of actual operation of a power plant, working conditions such as peak regulation, regulation and stop, power rise and the like in an operation stage are simulated, and a prediction mode from full power operation to designed fuel consumption is more accurate.
The production real-time data comprises the liquid level of the spent fuel pool, the temperature of the spent fuel pool, the flow of a spent fuel pool cooling water system, the inlet temperature of the spent fuel pool cooling water system, the flow and the temperature of a waste heat discharge system, the flow and the temperature of an equipment cooling water system, the flow and the temperature of passive containment cooling water and the flow and the temperature of fire fighting water. The boiling time of the spent fuel pool comprises the boiling time of pool water under the optimal working condition, the exposure time of a tube seat on an assembly under the optimal working condition, the boiling time of pool water under the limited working condition and the exposure time of a tube seat on an assembly under the limited working condition.
The system can realize real-time heat exchange calculation of the spent fuel pool through the real-time boiling time prediction system of the spent fuel pool. And (3) accurately calculating decay heat data of the fuel assembly by using a burn-up equation and combining actual operation power and a burn-up history of the power plant. Production data related to temperature rise of the spent fuel pool in the power plant is transmitted to the system, so that the temperature rise and boiling time of the spent fuel pool and the exposure time of a fuel assembly can be displayed in real time, the boiling time of the spent fuel pool is monitored accurately in real time, and reference is provided for decision under accidents.
The method for predicting the boiling time of the spent fuel pool in real time comprises the following steps
And S01, calculating the decay heat of the fuel assembly through a spent fuel decay heat calculation model and combining historical operation data of the fuel assembly. Specifically, the decay heat of the fuel assembly is calculated in real time through a burnup equation and inputting information such as the operation historical power, the loading and unloading time, the start-up time, the critical time, the shutdown time, the fuel assembly shutdown burnup and the like of the fuel assembly.
And calculating the real-time decay heat of the fuel assemblies stored in the spent fuel pool by using a burn-up equation-based method based on the information such as the operating power history, the shutdown time, the burn-up at the power change moment, the fuel-off burn-up, the enrichment degree of the fuel assemblies and the like of the fuel assemblies stored in the spent fuel pool. Due to the dynamic change of the field power history, when the fuel consumption is changed at the moment of the input power change, the fuel consumption at the moment with larger power change, such as shutdown, power reduction and power rise, is selected according to the power operation history. For small fluctuations in power during normal operation, the power variations can be ignored.
And S02, acquiring real-time production data related to the temperature change of the spent fuel pool. In order to realize the real-time prediction of the boiling time of the spent fuel pool and provide the boiling time of the spent fuel pool in real time according to the actual situation on site under the accident condition, the power plant parameters acquired by the production real-time data acquisition module are transmitted to an office network, and the real-time prediction system of the boiling time of the fuel pool can read the data in the production real-time data acquisition module, such as the real-time production data of the liquid level, the temperature, the flow of a cooling system and the like of the spent fuel pool, update the solving results of an equation set of the spent fuel system and the cooling water system in real time to acquire the accurate relation of the temperature of the spent fuel pool along with the time, thereby accurately calculating the temperature rise rate, the boiling time and the exposure time of the assembly of the spent fuel pool in real time and providing a basis for the decision response after the accident in time. Meanwhile, in order to deal with the situation that the real-time data production system is unavailable, a function of manually inputting the parameters is reserved. And under the accident condition, acquiring unit parameters according to methods such as an emergency system and conventional communication.
And S03, obtaining a function relation between the water temperature and the time of the spent fuel pool by calculating the parameters through the pool heat exchange calculation model and combining the decay heat of the fuel assembly and the production real-time data. The spent fuel pool heat exchange calculation model is mainly a double-system coupling model based on a first theorem of thermodynamics. The first system is a spent fuel body system, and the thermodynamic boundary is the interface between the outer surface of the fuel rod and the cooling water of a spent fuel pool; the second system is a spent fuel pool cooling water system, and thermodynamic boundaries are an interface between the outer surface of the fuel rod and spent fuel pool cooling water, a contact surface between the spent fuel pool cooling water and a pool wall, a free liquid level of the spent fuel pool and the atmospheric environment of the fuel plant, and a joint of each cooling water inlet/outlet connecting pipe and the spent fuel pool.
Based on the heat inflow and outflow in fig. 1, a coupled ordinary differential equation system of the spent fuel system and the cooling water system is constructed. The heat of the spent fuel system flows into the decay heat of the fuel assembly, and the heat flows out to transfer heat to the cooling water system; the heat of the cooling water system flows into the fuel assembly decay heat and passes through the heat convection heating cooling water, the two series of spent fuel cooling water, fire water, passive containment cooling water and normal waste heat discharging system cooling water, and the heat flows out of the fuel assembly decay heat and is discharged by the spent fuel cooling water, the spent fuel cooling water dissipates heat to air and the spent fuel cooling water dissipates heat to the wall surface.
The conservation of mass of spent fuel and spent fuel pool cooling water is assumed. The spent fuel is solid and does not change in the whole calculation process; the cooling water mass of the spent fuel pool maintains dynamic conservation under the condition of equal inlet and outlet flow, and the loss of the coolant mass caused by evaporation is ignored. And solving equations of the spent fuel system and the cooling water system by using a 4-order Runge-Kutta method (RK 4), and obtaining the function relation of the fuel temperature and the water temperature of the spent fuel pool and the time. In the solving process, the specific heat capacity at constant pressure is determined by taking the average value by adopting a statistical analysis method, and the specific enthalpy and the density of water are determined by adopting a linear regression method. The physical property parameter of the water is determined by the following steps, specifically comprising the following steps of S31 determining the specific heat capacity at constant pressure: through statistical analysis, the variance value of the constant-pressure specific heat capacity of water in the temperature interval is smaller, and the variance value is regarded as a constant when the water pool heat exchange calculation model is solved; s32 determines the specific enthalpy: calculating by using a linear regression equation, wherein the inlet temperature of each path of cooling water of the spent fuel pool is measured by a production real-time data acquisition module in real time, and the temperature corresponding to the specific enthalpy of an outlet is the temperature of the pool water; s33 determines density: the density of water is a function of temperature, the coefficient of linear correlation is higher in a given temperature interval of 0-100 ℃, and the density of water is calculated by using the linear regression equation thereof. In addition, the convective heat transfer model of the fuel assembly and the cooling water is the large space convective heat transfer of a stationary cylinder, and the Gravax number is used to calculate the total heat transfer coefficient.
And S04, predicting the boiling time of the spent fuel pool in real time according to the function relation between the water temperature of the spent fuel pool and the time. After the function relation between the water temperature of the spent fuel pool and the time is obtained, the boiling time of the spent fuel pool can be predicted. The method comprises the following steps: boiling time of pool water under the optimal working condition, exposure time of upper pipe seats of the components under the optimal working condition, boiling time of pool water under the limited working condition and exposure time of upper pipe seats of the components under the limited working condition. The evaluation of the spent fuel pool losing cooling and water replenishing capacity under the accident condition and the decision reference after the accident occur are met. The calculation flow of real-time heat exchange is shown in fig. 2.
According to the method, the boiling time of the spent fuel pool is monitored in real time by constructing a spent fuel decay heat calculation and pool heat exchange calculation model and providing input parameters required by temperature rise analysis in real time. Based on the method, the content of the temperature rise calculation of the spent fuel pool of the nuclear power plant at present is realized, and nuclear power plant personnel can analyze the heat exchange capacity of the spent fuel pool in real time, so that the method has obvious improvement compared with the traditional calculation mode.
The above-described embodiments are merely illustrative of the preferred embodiments of the present invention, and do not limit the spirit and scope of the present invention. Various modifications and improvements of the technical solutions of the present invention may be made by those skilled in the art without departing from the design concept of the present invention, and the technical contents of the present invention are all described in the claims.
Claims (2)
1. The spent fuel pool boiling time real-time prediction system is characterized in that: comprises that
The spent fuel decay heat calculation module is used for calculating the decay heat of the fuel assembly through a spent fuel decay heat calculation model and by combining historical operation data of the fuel assembly; the historical operating data comprises operating historical power, burnup at the moment of power change, loading and unloading time, reactor start time, critical time, reactor shutdown time and fuel assembly reactor shutdown burnup; the spent fuel decay heat calculation model is a fuel consumption equation;
the production real-time data acquisition module is used for acquiring production real-time data related to temperature change of the spent fuel pool; the production real-time data comprises the liquid level of the spent fuel pool, the temperature of the spent fuel pool, the flow of a spent fuel pool cooling water system, the inlet temperature of the spent fuel pool cooling water system, the flow and the temperature of a waste heat discharge system, the flow and the temperature of an equipment cooling water system, the flow and the temperature of passive containment cooling water and the flow and the temperature of fire fighting water;
the pool heat exchange calculation module is used for obtaining parameters through a pool heat exchange calculation model and combining decay heat of the fuel assembly and production real-time data to calculate and obtain a function relation between the water temperature of the spent fuel pool and time; the water pool heat exchange calculation model is a dual-system coupling model, and the dual-system coupling model is a coupling ordinary differential equation set of a spent fuel body system and a spent fuel pool cooling water system;
the spent fuel pool boiling time prediction module is used for predicting the spent fuel pool boiling time in real time according to the function relation between the water temperature of the spent fuel pool and the time; the boiling time of the spent fuel pool comprises the boiling time of pool water under the optimal working condition, the exposure time of a tube seat on an assembly under the optimal working condition, the boiling time of pool water under the limited working condition and the exposure time of the tube seat on the assembly under the limited working condition.
2. The method for predicting the boiling time of the spent fuel pool in real time adopts the system for predicting the boiling time of the spent fuel pool in real time as claimed in claim 1, and is characterized in that: comprises the following steps
S01, calculating decay heat of the fuel assembly through a spent fuel decay heat calculation model and by combining historical operation data of the fuel assembly;
s02, acquiring production real-time data related to temperature change of the spent fuel pool;
s03, obtaining a function relation between the water temperature and time of the spent fuel pool through a pool heat exchange calculation model and parameter calculation by combining decay heat of the fuel assembly and production real-time data; in the S03, the pool heat exchange calculation model is solved through a 4-order Lunge-Kutta method; the physical property parameter of the water in the S03 is determined by the following steps of S31: through statistical analysis, the variance value of the constant-pressure specific heat capacity of water in the temperature interval is smaller, and the variance value is regarded as a constant when the water pool heat exchange calculation model is solved; 32 determining the specific enthalpy: calculating by using a linear regression equation, wherein the inlet temperature of each path of cooling water of the spent fuel pool is measured by a production real-time data acquisition module in real time, and the temperature corresponding to the specific enthalpy of an outlet is the temperature of the pool water; s33 determines density: the density of water is a function of temperature, the coefficient of linear correlation is higher in a given temperature interval of 0-100 ℃, and the density of water is calculated by using a linear regression equation of the density of water; the convective heat transfer model of the fuel assembly and the cooling water in the S03 is large-space convective heat transfer of a static cylinder, and the total heat transfer coefficient is calculated by using the Gravav number;
and S04, predicting the boiling time of the spent fuel pool in real time according to the function relation between the water temperature of the spent fuel pool and the time.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010936983.5A CN112052998B (en) | 2020-09-08 | 2020-09-08 | Spent fuel pool boiling time real-time prediction system and method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010936983.5A CN112052998B (en) | 2020-09-08 | 2020-09-08 | Spent fuel pool boiling time real-time prediction system and method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112052998A CN112052998A (en) | 2020-12-08 |
| CN112052998B true CN112052998B (en) | 2023-04-07 |
Family
ID=73610407
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010936983.5A Active CN112052998B (en) | 2020-09-08 | 2020-09-08 | Spent fuel pool boiling time real-time prediction system and method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112052998B (en) |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101250750B1 (en) * | 2011-09-08 | 2013-04-04 | 한전원자력연료 주식회사 | Real-time monitoring system for spent fuel pool and method thereof |
| GB2530969B (en) * | 2014-06-04 | 2020-04-08 | Inst Jozef Stefan | Method and apparatus for assessing the state of a spent-fuel facility |
| CN111180094A (en) * | 2019-12-24 | 2020-05-19 | 福建福清核电有限公司 | Temperature rise calculation method for nuclear power plant spent fuel pool coolant loss accident |
-
2020
- 2020-09-08 CN CN202010936983.5A patent/CN112052998B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN112052998A (en) | 2020-12-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Gauntt et al. | Fukushima Daiichi accident study: status as of April 2012. | |
| CN110970142B (en) | Method for predicting emergency working condition of initiation of large-break water loss accident of pressurized water reactor | |
| CA3141470A1 (en) | Containment shell simulation test apparatus | |
| Dolganov | Possibility of misleading readings of water level in VVER steam generator during severe accidents with account for the Fukushima lessons | |
| CN112052998B (en) | Spent fuel pool boiling time real-time prediction system and method | |
| Rahgoshay et al. | Pressure distribution in the containment of VVER-1000 during the first seconds of large break LOCA | |
| Wang et al. | TRACE modeling and its verification using Maanshan PWR start-up tests | |
| US20210027901A1 (en) | Methods and systems for facilitating the management of reactor transient conditions associated with reactors | |
| Lin et al. | Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE | |
| Jeon et al. | Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation | |
| Safarzadeh et al. | The large-break LOCA uncertainty analysis in a VVER-1000 reactor using TRACE and DAKOTA | |
| Mitsuda et al. | Evaluation of the in-vessel heat transfer for the debris removal of the Fukushima Daiichi nuclear power plant | |
| Farman et al. | A Review of Advances in Pressurizer Response Research for Pressurized Water Reactor Systems. | |
| Pyrohov et al. | Analysis of accidents of the WWER-1000 reactor in which emergency cooling heat exchangers operate | |
| Povarov et al. | Developing and applying modern methods of leakage monitoring and state estimation of fuel at the Novovoronezh nuclear power plant | |
| Groudev et al. | Validation of RELAP5/MOD3. 2 model on trip off one main coolant pump for VVER 440/V230 | |
| Kim et al. | Development of RCS-containment coupled analysis model and evaluation of LBLOCA for APR-1400 | |
| Li | CFD Pre-test Analysis of SIMECO-2 Experiment | |
| Pistora et al. | Evaluation of pressurised thermal shocks for VVER 440/213 reactor pressure vessel in NPP Dukovany | |
| Lys et al. | Safety analysis of VVER fuel rod modelling in reactivity initiated accident | |
| Ning et al. | LBLOCA initiated emergency condition analysis for a China three-loop PWR | |
| Liu et al. | Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant | |
| Ohga | A computer program for assessment of emergency operation procedures under non-loca transient conditions in BWRs | |
| Yu et al. | Operation and Operation Analysis | |
| Cipiti | Molten Salt Test Loop Options to Support the DOE NE MSR Program. |
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 |