CN107910082B - Nuclear power station spent fuel reservoir heat exchanger performance test method - Google Patents
Nuclear power station spent fuel reservoir heat exchanger performance test method Download PDFInfo
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- CN107910082B CN107910082B CN201711128478.2A CN201711128478A CN107910082B CN 107910082 B CN107910082 B CN 107910082B CN 201711128478 A CN201711128478 A CN 201711128478A CN 107910082 B CN107910082 B CN 107910082B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a kind of nuclear power station spent fuel reservoir heat exchanger performance pilot systems, it is under Residual heat removal mode, pass through the heat exchanger of safety injection system, by primary Ioops heat transfer to component cooling water system, Spent Fuel Pool is heated by the heat exchanger of fuel pit purification and cooling system by component cooling water system again.The invention also discloses a kind of nuclear power station spent fuel reservoir heat exchanger performance test methods.Compared with the existing technology, Spent Fuel Pool heat exchanger performance pilot system and test method of the present invention are using different cold source systems as intermediary, gradually conduction primary Ioops heat to Spent Fuel Pool and is heated indirectly, the minimum temperature of Spent Fuel Pool when test has been determined, has taken into account the safety of primary Ioops unit allocation and medium system；By operating condition migration analysis, effective conversion of the acceptance criteria under different tests operating condition is analyzed, while having carried out the error analysis under operating condition of test, it is determined that tests accuracy of instrument requirement used.
Description
Technical field
The invention belongs to technical field of nuclear power, it is more particularly related to which a kind of nuclear power station spent fuel reservoir heat is handed over
Parallel operation performance test system and test method.
Background technique
Currently, the test of Spent Fuel Pool heat exchanger performance is to Spent Fuel Pool heat exchanger in technical field of nuclear power
The verifying of heat exchanger efficiency, can test result not only reacts heat exchanger meet design requirement, even more be directly related to nuclear power station
An important important indicator of safety work after reloading.
In the related technology, pressurized-water reactor nuclear power plant unit Spent Fuel Pool heat exchanger is equally used as primary Ioops refrigerating mode
Spare cold source design scheme can reversely heat spentnuclear fuel by the hot water that primary Ioops during joint debugging generate when carrying out test and executing
Pond heat exchanger carries out the heating of water in Spent Fuel Pool.It is another in the related technology, pressurized-water reactor nuclear power plant unit spentnuclear fuel water
The cooling scheme in pond is the three independent enclosed cooling circuits of column, with primary Ioops and related system without directly contacting, Bu Nengzhi
It connects by the hot water of primary Ioops and carries out effectiveness of heat exchanger test.This design method makes Spent Fuel Pool in the debugging stage
Heat source can not easily be obtained.
Currently, in three generations's nuclear power technology heap-type, it is planned that the test of weary pond effectiveness of heat exchanger is placed into unit Shang Yunhou
First fuel cycle after execute, using directly being tested after the weary water heating of the heat release of irradiated fuel assembly.But
Above-mentioned technical proposal has some limitations: (1) weary water temperature is influenced by spentnuclear fuel heat release after reloading, and weary water temperature needs to protect
It holds in a certain range, temperature regulating range is limited during test；(2) water that test uses contains certain radioactivity, if hot
Exchanger efficiency is unsatisfactory for requiring to need to re-replace or carry out necessary modification, and Spent Fuel Pool will be unsatisfactory for redundancy cold source and set
Meter, and enforcement difficulty is larger；(3) test executes window and is limited, and is unsatisfactory for the safety prison that this domestic test need to be completed before charging
Superintend and direct requirement.
Currently, there are also the sides using " interim electric heater+water circulating pump experimental rig " in three generations's nuclear power technology heap-type
Case extracts the water in Spent Fuel Pool using water circulating pump, and water is returned to weary combustion using after several groups of high-power electric heater heating
The mode of material pool circulating heating water is tested.But there is also certain limitations for above-mentioned technical proposal: (1) interim
Device need to purchase high-power heater and water circulating pump, and device need to be fabricated separately, costly；(2) it needs to heat during testing
Nearly 1600 cubic metres of weary waters, heating time is long, and heater power consumption is big；(3) interim electricity need to be laid using interim heating device
Cable, interim water pipe etc., it is heavy workload, long in time limit, at high cost.
In view of this, it is necessory to provide a kind of nuclear power station spent fuel reservoir heat high-efficient, at low cost and safe and reliable
Exchanger performance pilot system and test method.
Summary of the invention
It is an object of the invention to: it overcomes the deficiencies of the prior art and provide a kind of high-efficient, at low cost and safe and reliable
Nuclear power station spent fuel reservoir heat exchanger performance pilot system and test method.
In order to achieve the above-mentioned object of the invention, the present invention provides a kind of tests of nuclear power station spent fuel reservoir heat exchanger performance
System, the pilot system pass through the heat of safety injection system (abbreviation RIS system) under Residual heat removal (abbreviation RHR) mode
Exchanger passes through fuel pit by primary Ioops heat transfer to component cooling water system (abbreviation RRI system), then by RRI system
The heat exchanger of purification and cooling system (abbreviation PTR system), Spent Fuel Pool is heated.
In order to achieve the above-mentioned object of the invention, the present invention also provides a kind of examinations of nuclear power station spent fuel reservoir heat exchanger performance
Proved recipe method, comprising the following steps:
1) determine RRI system operation maximum temperature and primary Ioops temperature range, build RIS system heat exchanger and
The heating power simulation model of the heat exchanger of PTR system analyzes the water temperature target value of Spent Fuel Pool；
2) model simultaneously board design operating condition to the heat exchanger of PTR system, obtain maximum fouling resistance coefficient；
3) using maximum fouling resistance coefficient, and determine that the examination under different tests operating condition is quasi- according to heat exchange formula
Then；
4) error of thermometric instrument is obtained by standard error function；
5) error of flowmeter is calculated by the parameter of flowmeter.
As a kind of improvement of nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention, the primary Ioops temperature
Degree is 60~65 degrees Celsius.
As a kind of improvement of nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention, the RRI system
Inversely it is heated to 48 degrees Celsius.
As a kind of improvement of nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention, the spentnuclear fuel water
Pond is heated to 45 degrees Celsius.
As a kind of improvement of nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention, the test is selected
AA grades of precision of Pt100 platinum resistance thermometer sensor,.
As a kind of improvement of nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention, the operating condition of test
Under, PTR system entry temperature setting is 45 degrees Celsius.
As a kind of improvement of nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention, the flowmeter
The pressure difference from flow-through orifice is measured, converts to obtain flow measurement error formula by flow formula.
Compared with the existing technology, nuclear power station spent fuel reservoir heat exchanger performance pilot system and test method benefit of the present invention
Use different cold source systems as intermediary, gradually conduction primary Ioops heat to Spent Fuel Pool and is heated indirectly, really
The minimum temperature for having determined Spent Fuel Pool when test, ensure that the progress of test, and taken into account primary Ioops unit allocation and matchmaker
The safety of Jie's system；By operating condition migration analysis, effective conversion of the acceptance criteria under different tests operating condition is analyzed, is carried out simultaneously
Error analysis under operating condition of test, it is determined that test accuracy of instrument requirement used, demonstrate the enforceability of the program.
Detailed description of the invention
With reference to the accompanying drawings and detailed description, nuclear power station spent fuel reservoir heat exchanger performance of the present invention is tested and is
System and test method are described in detail, in which:
The scheme that Fig. 1 show nuclear power station spent fuel reservoir heat exchanger performance pilot system and test method of the present invention is shown
It is intended to.
Specific embodiment
In order to be more clear goal of the invention of the invention, technical solution and its advantageous effects, below in conjunction with attached drawing
And specific embodiment, the present invention will be described in further detail.It should be understood that specific reality described in this specification
Mode is applied just for the sake of explaining the present invention, is not intended to limit the present invention.
Refering to Figure 1, nuclear power station spent fuel reservoir heat exchanger performance pilot system of the present invention is under RHR mode,
By the heat exchanger of RIS system 20,10 heat transfer of primary Ioops is passed through into PTR system to RRI system 30, then by RRI system 30
The heat exchanger of system 40, Spent Fuel Pool 50 is heated.
Nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention the following steps are included:
1) temperature range for determining the maximum temperature and primary Ioops 10 that RRI system 30 is run, the heat for building RIS system 20 are handed over
The heating power simulation model of parallel operation and the heat exchanger of PTR system 40 analyzes the water temperature target value of Spent Fuel Pool 50；
2) model simultaneously board design operating condition to the heat exchanger of PTR system 40, obtain maximum fouling resistance coefficient；
3) using maximum fouling resistance coefficient, and determine that the examination under different tests operating condition is quasi- according to heat exchange formula
Then；
4) error of thermometric instrument is obtained by standard error function；
5) error of flowmeter is calculated by the parameter of flowmeter.
One, Spent Fuel Pool is reversed the analysis of heating temperature
In conjunction with the practical feelings of each related system in nuclear power station spent fuel reservoir heat exchanger performance test method of the present invention
Condition determines the maximum temperature that each system can achieve at runtime, and the maximum temperature of heating Spent Fuel Pool 50 is determined with this.
1) during joint debugging, when RIS system 20 carries out the cooling of primary Ioops 10 with RHR mode, the normal of primary Ioops 10 is accessed
Temperature is 120 DEG C, and it is 180 DEG C that highest, which bears design temperature,；
2) RRI system 30 (EPR unit RRI system 30 uses carbon steel pipe) when temperature is more than 48 DEG C, facing before pump
When strainer be easy to block.In conjunction with the operating experience of daily single system, 30 highest of RRI system can be stablized under conditions of 48 DEG C
Operation.Accordingly, it is determined that the water of 30 side of RRI system is heated to 48 DEG C by the heat exchanger of RIS system 20 by primary Ioops 10, finally
48 DEG C of component cooling water is heated Spent Fuel Pool 50 by the heat exchanger of the main cooling column of PTR system 40；
3) by building the thermodynamic model of the heat exchanger of RIS system 20, the heat exchanger of PTR system 40, to carry out simulation imitative
Very, the component cooling water for demonstrating 48 DEG C has the ability that Spent Fuel Pool 50 is heated to 45 DEG C；
4) meet RRI system 30 is inversely heated to 48 DEG C under the premise of, it is contemplated that the unit at high temperature of primary Ioops 10
10 temperature of primary Ioops when test is determined as 60~65 DEG C by the degree of difficulty and temperature transient risk of control.
Therefore, pass through network analysis, it is determined that the temperature parameter of related system when reverse scheme is implemented:
Test platform: 10 temperature of primary Ioops is 60~65 DEG C；
Medium system temperature: RRI system 30 is reversely heated to 48 DEG C；
Weary water temperature target value: Spent Fuel Pool 50, which is reversed, is heated to 45 DEG C.
Two, effective conversion of the test acceptance criteria under different operating conditions
It determines test acceptance criteria and the error analysis under this testing program, is to determine fuel pit heat exchange of the present invention
The whether feasible committed step of device method for testing performance.
1) equivalency transform of acceptance criteria
The design requirement of EPR unit Spent Fuel Pool 50 is as shown in table 1.Wherein, the main cooling column of PTR system 40 require stopping
Under heap DBC1 operating condition, maintain Spent Fuel Pool 50 at 50 DEG C hereinafter, transmission heat is 11.46MW；In 30 high flow capacity of RRI system
Under DBC2-DECB accident, it is desirable that maintain Spent Fuel Pool 50 at 80 DEG C hereinafter, transimission power is 6.69MW；For PTR system 40
3rd cooling column then require under 95 DEG C of operating condition, and transmission heat is 22.76MW.
There is formula for heat exchanger:
Q=FKS × Δ Tlm
It converts:
Wherein, FKS is total heat transfer coefficient (W/ DEG C), and F is the dimensionless empirical calibration factor, and K is heat exchanger heat transfer system
Number, S are heat transfer area (m2), Δ TlmFor mean logarithmic temperature difference, and Δ TlmExpression formula are as follows:
The requirement of 1 heat exchanger designs of table
The FKS of heat exchanger changes with fluid temperature (F.T.), but fouling resistance coefficient hardly follows temperature change.Only
Guarantee that maximum fouling resistance coefficient is constant, design requirement can be moved to operating condition of test.Simulate the design work of heat exchanger
Condition, obtains the maximum dirtiness resistance of permission, and then calculates in maximum thermal resistance coefficient heat exchanger in the case where testing worst cold case
Exchange capability of heat can be used as the acceptance criteria under operating condition of test.Therefore, it is necessary to analyze heat exchanger modeling.
It is modeled using heat exchanger of the HTRI software to PTR system 40, by the outer shape parameter for defining heat exchanger
(including heat exchanger type, tube bank arrangement, baffling board parameter etc.) and fluid thermodynamic parameter, it is imitative to carry out modeling to heat exchanger
Very, for analyzing the theoretical coefficient of heat transfer of heat exchanger.Since the performance parameters such as material are in software inhouse specific definition, because
The heat transfer coefficient of material can be used for simulation calculation under this different temperatures.
Acceptance criteria of 2 heat exchanger of table under operating condition of test
The cooling column of third of PTR heat exchanger 40 are chosen to analyze, the flow velocity of PTR heat exchanger 40 is under design conditions
95 DEG C of 147kg/s, PTR system entry temperature, EVU system flow rate are 170kg/s, and the inlet temperature of EVU system is 45 DEG C, simulation
Calculate heat exchanger theory FKS clean under the operating condition is 3.708MW/ DEG C.It is 30E-6m in pipe side thermal resistivity2K/W, shell
Side thermal resistivity is 60E-6m2When K/W, heat exchange amount 22.76MW, FKS are 1.505MW/ DEG C, and exchange capability of heat is exactly equal to design
It is required that.Under operating condition of test, PTR system entry temperature setting is 45 DEG C, the setting root of containment heat derives system EVU temperature
It is determined according to practical operation situation.
Weary combustion is simulated using the maximum fouling resistance coefficient as basic parameter in order to demonstrate the calculation method of operating condition migration
Expect that pond 50 is only 50 DEG C of operating condition of test.50 DEG C are set by the inlet temperature of PTR system 40, the inlet temperature of EVU system
31 DEG C are set as, it is 8.370MW that heat exchange amount, which is calculated, and FKS numerical value is 1.239MW/ DEG C.Heat transfer coefficient FKS, which can be used as, to be tried
The acceptance criteria of (50 DEG C of the inlet temperature of PTR system 40,31 DEG C of EVU system entry temperature) is tested under operating condition.It can similarly calculate
Acceptance criteria under different tests operating condition out, as shown in table 2.
Three, the calculating of instrument uncertainty during testing
For the exchange capability of heat of heat exchanger, just like giving a definition and calculate:
Wherein:
K is total heat transfer coefficient, unit W/m2*K；
S is heat transfer surface area, unit m2；
ΔTlmFor logarithmic mean temperature, unit DEG C；
F is that the dimensionless experiential modification factor needs to repair if two side liquid of heat exchanger is not complete reverse flow
Just.
According to heat exchanger heat transfer rate formula above it is found that the uncertainty calculation of heat exchanger be related to thermometric instrument and
Flow instrument.Instrument error can be calculated separately out by uncertainty function calculation formula:
1) what test used is all Pt100 platinum resistance thermometer sensor, for different grades of platinum resistance thermometer sensor, there is standard error function:
Class AA dT=± (0.10 DEG C+0.0017 × | T |)
Class A dT=± (0.15 DEG C+0.002 × | T |)
Selecting precision is AA grades of thermometric instrument, and when uses high-precision recorder, and (registration accuracy of keithley2701 can
To reach 0.1 DEG C), finally the error of instrument is as shown in table 3 on the spot:
The final instrument error on the spot of table 3
2) pressure difference of the measurement of flowmeter from flow-through orifice, formula are as follows:
Wherein:
QMFor the flow measured；
K is discharge coefficient；
A is constant；
D is hole board diameter；
Δ p is orifice plate upstream and downstream differential pressure；
ρ is fluid density.
By conversion, following formula is obtained:
Wherein:
εQFor flow measurement error, unit m3/h；
QMFor the flow of measurement, unit m3/h；
εkFor discharge coefficient error, unit %；
εSFor Δ p differential pressure Watch Error, unit %；
QMAXFor greatest physical range.
Above calculating parameter can be consulted from the parameter list of flowmeter and be obtained.The mistake of flowmeter can be calculated
It is poor as shown in table 4.
In conjunction with can be seen that compared with the existing technology to the detailed description of embodiment of the present invention above, nuclear power of the present invention
Spent Fuel Pool heat exchanger performance pilot system of standing and test method are using different cold source systems as intermediary, gradually
Conduction 10 heat of primary Ioops to Spent Fuel Pool and is heated indirectly, it is determined that the lowest temperature of Spent Fuel Pool 50 when test
Degree, ensure that the progress of test, and taken into account the safety of primary Ioops 10 unit allocation and medium system；Pass through operating condition migration point
Analysis analyzes effective conversion of the acceptance criteria under different tests operating condition, while having carried out the error analysis under operating condition of test, determines
Test accuracy of instrument requirement used, demonstrates the enforceability of scheme.
4 flow Watch Error of table
According to the disclosure and teachings of the above specification, those skilled in the art in the invention can also be to above-mentioned embodiment party
Formula carries out change and modification appropriate.Therefore, the invention is not limited to the specific embodiments disclosed and described above, to this
Some modifications and changes of invention should also be as falling into the scope of the claims of the present invention.In addition, although this specification
In use some specific terms, these terms are merely for convenience of description, does not limit the present invention in any way.
Claims (7)
1. a kind of nuclear power station spent fuel reservoir heat exchanger performance test method, which is characterized in that be used for Nuclear Power Station's Exhausted Fuels water
Pond heat exchanger performance pilot system, the pilot system is under RHR mode, by the heat exchanger of RIS system, by primary Ioops
Heat transfer is heated Spent Fuel Pool by the heat exchanger of PTR system to RRI system, then by RRI system；The test
Method the following steps are included:
1) maximum temperature of RRI system operation and the temperature range of primary Ioops are determined, the heat exchanger and PTR of RIS system are built
The heating power simulation model of the heat exchanger of system analyzes the water temperature target value of Spent Fuel Pool；
2) model simultaneously board design operating condition to the heat exchanger of PTR system, obtain maximum fouling resistance coefficient；
3) using maximum fouling resistance coefficient, and the acceptance criteria under different tests operating condition is determined according to heat exchange formula；
4) error of thermometric instrument is obtained by standard error function；
5) error of flowmeter is calculated by the parameter of flowmeter.
2. nuclear power station spent fuel reservoir heat exchanger performance test method according to claim 1, which is characterized in that described
Primary Ioops temperature is 60~65 degrees Celsius.
3. nuclear power station spent fuel reservoir heat exchanger performance test method according to claim 1, which is characterized in that described
RRI system is inversely heated to 48 degrees Celsius.
4. nuclear power station spent fuel reservoir heat exchanger performance test method according to claim 1, which is characterized in that described
Spent Fuel Pool is heated to 45 degrees Celsius.
5. nuclear power station spent fuel reservoir heat exchanger performance test method according to claim 1, which is characterized in that described
Precision AA grades of Pt100 platinum resistance thermometer sensor, is selected in test.
6. nuclear power station spent fuel reservoir heat exchanger performance test method according to claim 1, which is characterized in that described
Under operating condition of test, PTR system entry temperature setting is 45 degrees Celsius.
7. nuclear power station spent fuel reservoir heat exchanger performance test method according to claim 1, which is characterized in that described
Pressure difference of the measurement of flowmeter from flow-through orifice converts to obtain flow measurement error formula by flow formula.
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| CN112361948B (en) * | 2020-10-29 | 2022-02-22 | 中国核动力研究设计院 | Heating device for simulating different temperature control of fuel rod-spent pool |
| CN113109386B (en) * | 2021-04-01 | 2023-04-28 | 山东核电有限公司 | Thermal state performance acceptance method for plate heat exchanger of AP1000 nuclear power station |
| CN113379302B (en) * | 2021-06-29 | 2024-01-19 | 广东核电合营有限公司 | Nuclear power station chemical efficiency control method, device, equipment and storage medium |
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| US9779841B2 (en) * | 2014-02-21 | 2017-10-03 | Dw James Consulting, Llc | Process for the accurate characterization of low level nuclear waste |
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| CN103811084A (en) * | 2012-11-14 | 2014-05-21 | 中国广东核电集团有限公司 | Pre-commissioning preparation method of nuclear power station waste heat discharging system |
| US9779841B2 (en) * | 2014-02-21 | 2017-10-03 | Dw James Consulting, Llc | Process for the accurate characterization of low level nuclear waste |
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