CN106128528A - A kind of method and apparatus monitoring nuclear power plant reactor pressure vessel irradiation damage - Google Patents
A kind of method and apparatus monitoring nuclear power plant reactor pressure vessel irradiation damage Download PDFInfo
- Publication number
- CN106128528A CN106128528A CN201610614794.XA CN201610614794A CN106128528A CN 106128528 A CN106128528 A CN 106128528A CN 201610614794 A CN201610614794 A CN 201610614794A CN 106128528 A CN106128528 A CN 106128528A
- Authority
- CN
- China
- Prior art keywords
- pressure vessel
- reactor pressure
- initially
- real
- irradiation damage
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of method and apparatus monitoring reactor pressure vessel irradiation damage, calculate the rate of change of resistivity after described reactor pressure vessel steel irradiation damage by the resistivity after recording the initial electrical resistivity of reactor pressure vessel steel and obtaining in real time the described reactor pressure vessel steel irradiation damage of random time point；And obtain the situation of change of described reactor pressure vessel steel macro-mechanical property parameter in irradiation damage according to the rate of change of resistivity after described irradiation damage；And then the irradiation damage degree of described reactor pressure vessel is assessed according to described macro-mechanical property Parameter analysis.The method and device economy, environmental protection, safe efficient, the irradiation damage degree at the multiple position of reactor pressure vessel (including specific part) can be monitored in real time.
Description
Technical field
The present invention relates to nuclear power plant reactor pressure vessel safety and run field, particularly relate to one and monitor core in real time
The method of power station reactor pressure vessel irradiation damage.
Background technology
Nuclear power plant reactor pressure vessel is for disposing nuclear reactor and bearing the hermetic container of its huge operating pressure,
Wherein contain and be supported with reactor core nuclear fuel assembly, control assembly, in-pile component and reactor coolant.It is due to long service
In strong irradiation, high temperature, environment under high pressure, easily there is neutron irradiation damage, be embodied in reactor pressure vessel steel radiation embrittlement
During intensity raise, toughness decline, further result in reactor pressure vessel effect lost efficacy.
At present, China is in-service, be manganese nickel molybdenum low-alloy steel material at the reactor pressure vessel steel building nuclear power station, France
The AFCEN trade mark is 16MND5, is similar to U.S. ASME trade mark SA-508-III steel.Run in order to ensure reactor pressure vessel
Safety, mainly carrys out the irradiation damage degree to reactor pressure vessel steel by the method for irradiation in currently available technology
It is monitored and evaluates.Specific implementation method is as follows: (1) nuclear power station first fuel loading run before, at reactor pressure vessel
Internally installed 4 to 6 irradiation monitoring pipes, every irradiation monitoring pipe is built with mechanical property examinations such as a number of stretching, impacts
Sample；(2) according to irradiation outline, utilize nuclear power station reload maintenance chance, periodically extract from reactor pressure vessel
Above-mentioned irradiation monitoring pipe, installs long-distance transport after radiation protection requires packaging and, to the hot cell mechanism of fixed point, dissects and take out stretching, punching
The mechanical property sample such as hit and carry out Mechanics Performance Testing, it is thus achieved that the tensile property of irradiation control sample and ductile-brittle transiton curve, obtain
Obtain the mechanical performance data after reactor pressure vessel steel irradiation；(3) according to above-mentioned mechanical performance data analytical reactions heap pressure
The irradiation damage degree of container steel, and then carry out the assessment for structural integrity of reactor pressure vessel and adjust reactor in good time
The operational factor etc. of system.
But said method has the drawback that
(1) being limited to the inner space of reactor pressure vessel, the irradiation monitoring pipe quantity that can load is extremely limited, it is impossible to
Multiple positions (including specific part) of reactor pressure vessel are monitored, and above-mentioned irradiation monitoring pipe must fill first
Before material runs, disposable loading is complete, can not supplement installation irradiation monitoring pipe in running, it is impossible to fully meet nuclear power in the future
Irradiation requirement to reactor pressure vessel time lengthening the life in station；
(2) after irradiation monitoring pipe extracts from reactor pressure vessel, it is necessary to transport the most at a distance from nuclear power station is long-distance
Transport to pinpoint hot cell mechanism, and the most domestic only Sichuan and two, Beijing unit possess this hot cell, and due to irradiation
Pipe has the highest hot, and therefore the security requirement in transportation is the highest, cost of transportation big, the cycle is long；
(3) belong to destructive testing due to the Mechanics Performance Testing of irradiation control sample, will produce after therefore having tested
A large amount of radwastes, follow-up three-protection design amount is relatively big, and cost is high；
(4) deriving from the clout of core region forging due to irradiation control sample, therefore said method is only capable of supervising on the whole
The degree of injury of control reactor pressure vessel reactor core district irradiation, it is impossible to other parts of monitoring reactor pressure vessel, especially
It it is the irradiation damage degree of ad-hoc location.
(5) said method does not possess the ability realizing monitoring reactor pressure vessel steel irradiation damage, only can obtain some
The irradiation damage degree of the reactor pressure vessel steel of particular point in time (depending on that irradiation monitoring pipe extracts the time).
It is therefore desirable to provide a kind of economy, environmental protection, safe efficient, the multiple portion of reactor pressure vessel can be monitored in real time
The nuclear power plant reactor pressure vessel irradiation damage monitoring method of position (including specific part) irradiation damage.
Summary of the invention
For in above-mentioned tradition irradiation method monitoring and evaluation response core pressure vessel steel irradiation damage degree method
The various problems existed, the invention provides a kind of economy, environmental protection, safe efficient, can monitor reactor pressure vessel in real time many
The nuclear power plant reactor pressure vessel irradiation damage monitoring method of individual position (including specific part) irradiation damage.
The technical scheme that the present invention proposes with regard to above-mentioned technical problem is as follows:
On the one hand, it is provided that a kind of side being monitored reactor pressure vessel irradiation damage by the change of monitoring resistor rate in real time
Method, comprises the steps:
S1, set up benchmark: record initial electrical resistivity ρ of reactor pressure vessel steel0；
S2, in real time monitoring: in nuclear power station properly functioning period, obtain the described reactor pressure of certain particular point in time in real time
Electricalresistivityρ after force container steel irradiation damage；
S3, analytical calculation: based on described initial electrical resistivity ρ0With the described reactor pressure vessel steel monitoring gained in real time
Electricalresistivityρ after irradiation damage calculates the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage；And root
Described reactor pressure vessel steel macromechanics in irradiation damage is obtained according to the rate of change δ (ρ) of resistivity after described damage
Performance parameter；
S4, security evaluation: assess the irradiation of described reactor pressure vessel according to described macro-mechanical property Parameter analysis
Injury tolerance.
Preferably, described macro-mechanical property parameter is real-time tensile strength Rm, real-time yield strength Rp0.2, in real time upper flat
Platform energy USE and in real time nil ductility temperature RTNDTIn at least one.
Preferably, in step S1, described initial electrical resistivity ρ0The process that records be: install at described reactor pressure vessel
After putting in place, and before nuclear power station first fuel loading runs, record initial electrical resistivity ρ of described reactor pressure vessel steel0。
Preferably, in step S1, during nuclear power station heat is tried, record described initial electrical resistivity ρ0。
Preferably, step S3 comprises the steps:
S3a, calculate the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage:
The rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage is calculated, wherein according to formula (1)
Described formula (1) is:
δ (ρ)=(ρ-ρ0)/ρ0 (1)
S3b, foundation formula (2-1)-(2-4) calculate described reactor pressure vessel steel tensile strength R in irradiation damagem
Rate of change δ (Rm), real-time yield strength Rp0.2Rate of change δ (Rp0.2), real-time upper mounting plate energy USE rate of change δ (USE) and real
Time nil ductility temperature RTNDTRate of change δ (RTNDTAt least one in), wherein said formula (2-1)-(2-4) is respectively as follows:
δ(Rm)=λ1·δ(ρ) (2-1)
δ(Rp0.2)=λ2·δ(ρ) (2-2)
δ (USE)=λ3·δ(ρ) (2-3)
δ(RTNDT)=λ4·δ(ρ) (2-4)
Wherein: λ1, λ2, λ3And λ4Being proportionality coefficient, usual span is 0.85-1.35, its value influence factor
Including: the Microstructure characteristics of reactor pressure vessel steel original state and nuclear power station run duration pile neutron irradiation field
Power spectrum；
S3c, according to formula (3-1)-(3-4), to calculate described reactor pressure vessel steel real-time tension in irradiation damage strong
Degree Rm, real-time yield strength Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one,
Wherein said formula (3-1)-(3-4) is respectively as follows:
δ(Rm)=[Rm-(Rm)Initially]/(Rm)Initially (3-1)
δ(Rp0.2)=[Rp0.2-(Rp0.2)Initially]/(Rp0.2)Initially (3-2)
δ (USE)=[USE-(USE)Initially]/(USE)Initially (3-3)
δ(RTNDT)=[RTNDT-(RTNDT)Initially]/(RTNDT)Initially (3-4)
Wherein: (Rm)InitiallyTensile strength for reactor pressure vessel steel original state；
(Rp0.2)InitiallyYield strength for reactor pressure vessel steel original state；
(USE)InitiallyUpper mounting plate energy for reactor pressure vessel steel original state；
(RTNDT)InitiallyNil ductility temperature for reactor pressure vessel steel original state；
Above-mentioned (Rm)Initially,(Rp0.2)Initially、(USE)InitiallyAnd (RTNDT)InitiallyAll can be from reactor pressure vessel equipment manufacturing
In the equipment complete report provided, inquiry obtains.
Preferably for specific nuclear power station and reactor pressure vessel, above-mentioned λ1, λ2, λ3And λ4Also can be by tradition
Irradiation control sample mechanical property test determined or revised.
Preferably, the security evaluation process in step S4 is: by described real-time tensile strength Rm, real-time yield strength Rp0.2、
Upper mounting plate energy USE and in real time nil ductility temperature RT in real timeNDTIn at least one as analyze input parameter, according to
Described input parameter of analyzing carries out security evaluation to the irradiation damage degree of described reactor pressure vessel.
Preferably, described according to described analyze input parameter the irradiation damage degree of described reactor pressure vessel is pacified
The step of full assessment includes: arrange pre-conditioned, when the described numerical value analyzing input parameter meet described pre-conditioned time, send
Early warning.
On the other hand, additionally provide a kind of change by monitoring resistor rate and monitor reactor pressure vessel irradiation damage in real time
The device of wound, including:
Detector unit and assessment unit, described detector unit one end coupled reaction core pressure vessel, be used for detecting reaction
The resistivity of core pressure vessel steel, the other end connects described assessment unit；Described assessment unit for according to described in detect
The resistivity of reactor pressure vessel steel calculates the rate of change of resistivity after described reactor pressure vessel steel irradiation damage,
And calculate reactor pressure vessel steel according to the rate of change of resistivity after described reactor pressure vessel steel irradiation damage and exist
Macro-mechanical property parameter in irradiation damage, and according to described macro-mechanical property parameter to described reactor pressure vessel
Irradiation damage degree carries out security evaluation.
Preferably, the resistance of described reactor pressure vessel steel is: after described reactor pressure vessel is installed and put in place,
And before nuclear power station first fuel loading runs, initial electrical resistivity ρ of the described reactor pressure vessel steel recorded0, and at core
Power station properly functioning period, the electricity after the described reactor pressure vessel steel irradiation damage of certain particular point in time recorded in real time
Resistance rate ρ.
Preferably, described assessment unit includes memory element, for storing the described reaction that described detector unit detects
The resistivity of core pressure vessel steel；Computing unit, the resistrivity meter of the reactor pressure vessel steel for detecting described in basis
Calculate and draw the rate of change of resistivity after described reactor pressure vessel steel irradiation damage, and according to described reactor pressure vessel steel
After irradiation damage, the rate of change of resistivity calculates reactor pressure vessel steel macro-mechanical property ginseng in irradiation damage
Number；And judging unit, for according to described in the reactor pressure vessel steel that the calculates macromechanics in irradiation damage
Performance parameter carries out security evaluation to the irradiation damage degree of described reactor pressure vessel.
Preferably, the resistance calculations of the reactor pressure vessel steel detected described in described basis draws described reactor pressure
After force container steel irradiation damage, the process of the rate of change of resistivity is: calculate described reactor pressure vessel steel according to formula (1)
The rate of change δ (ρ) of resistivity after irradiation damage, wherein said formula (1) is:
δ (ρ)=(ρ-ρ0)/ρ0 (1)。
Preferably, described macro-mechanical property parameter is real-time tensile strength Rm, real-time yield strength Rp0.2, in real time upper flat
Platform energy USE and in real time nil ductility temperature RTNDTIn at least one.
Preferably, described calculate instead according to the rate of change of resistivity after described reactor pressure vessel steel irradiation damage
The process answering core pressure vessel steel macro-mechanical property parameter in irradiation damage is:
Described reactor pressure vessel steel tensile strength R in irradiation damage is calculated according to formula (2-1)-(2-4)mChange
Rate δ (Rm), real-time yield strength Rp0.2Rate of change δ (Rp0.2), real-time upper mounting plate energy USE rate of change δ (USE) and real-time nothing
Ductility transition temperature RTNDTRate of change δ (RTNDTAt least one in), wherein said formula (2-1)-(2-4) is respectively as follows:
δ(Rm)=λ1·δ(ρ) (2-1)
δ(Rp0.2)=λ2·δ(ρ) (2-2)
δ (USE)=λ3·δ(ρ) (2-3)
δ(RTNDT)=λ4·δ(ρ) (2-4)
Wherein: λ1, λ2, λ3And λ4Being proportionality coefficient, usual span is 0.85-1.35, its value influence factor
Including: the Microstructure characteristics of reactor pressure vessel steel original state and nuclear power station run duration pile neutron irradiation field
Power spectrum；
The described reactor pressure vessel steel real-time tension in irradiation damage is calculated again strong according to formula (3-1)-(3-4)
Degree Rm, real-time yield strength Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one,
Wherein said formula (3-1)-(3-4) is respectively as follows:
δ(Rm)=[Rm-(Rm)Initially]/(Rm)Initially (3-1)
δ(Rp0.2)=[Rp0.2-(Rp0.2)Initially]/(Rp0.2)Initially (3-2)
δ (USE)=[USE-(USE)Initially]/(USE)Initially (3-3)
δ(RTNDT)=[RTNDT-(RTNDT)Initially]/(RTNDT)Initially (3-4)
Wherein: (Rm)InitiallyTensile strength for reactor pressure vessel steel original state；
(Rp0.2)InitiallyYield strength for reactor pressure vessel steel original state；
(USE)InitiallyUpper mounting plate energy for reactor pressure vessel steel original state；
(RTNDT)InitiallyNil ductility temperature for reactor pressure vessel steel original state；
Above-mentioned (Rm)Initially,(Rp0.2)Initially、(USE)InitiallyAnd (RTNDT)InitiallyAll can be from reactor pressure vessel equipment manufacturing
In the equipment complete report provided, inquiry obtains.
Preferably, arrange pre-conditioned in described judging unit, by described real-time tensile strength Rm, real-time yield strength
Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one as analyze input parameter
Input described judging unit, when described analyze input parameter numerical value meet described pre-conditioned time, described judging unit sends
Early warning.
Preferably, described device also includes display unit, and described display unit connects described assessment unit, is used for showing institute
State macro-mechanical property parameter and the safety of described reactor pressure vessel irradiation damage degree is assessed fruit.
Technical scheme has the following technical effect that
(1) can the resistivity of real-time testing nuclear power station run duration reactor pressure vessel steel, and calculate in real time and obtain out
The mechanical property delta data of reactor pressure vessel steel；
(2) it is lossless due to the resistivity measurement of reactor pressure vessel steel, therefore in the phase in nuclear power station full longevity, including not
Run duration of lengthening the life unlimited test can obtain data；
(3) test equipment and operation need not special radiological safety protection requirement, and test equipment space to external world without
Particular/special requirement, with low cost, safety good, does not the most produce radwaste, substantially without three-protection design demand；
(4) the irradiation damage degree of the multiple position of reactor pressure vessel can be monitored simultaneously, be particularly suited for monitoring in-service
The micro-crack found during inspection or the germinating of doubtful micro-crack, propagation behavior.
Accompanying drawing explanation
For the technical scheme being illustrated more clearly that in the embodiment of the present invention, in embodiment being described below required for make
Accompanying drawing be briefly described, it should be apparent that, below describe in accompanying drawing be only some embodiments of the present invention, for
From the point of view of those of ordinary skill in the art, on the premise of not paying creative work, it is also possible to obtain other according to these accompanying drawings
Accompanying drawing.
Fig. 1 is the method step flow process monitoring reactor pressure vessel irradiation damage in real time that the embodiment of the present invention one provides
Figure；
Fig. 2 is the apparatus structure signal of the reactor pressure vessel irradiation damage of monitoring in real time that the embodiment of the present invention two provides
Figure.
Detailed description of the invention
The present invention is directed to present in existing reactor pressure vessel irradiation damage supervision technology: existing reactor pressure holds
Device irradiation damage measure of supervision is due to the irradiation monitoring pipe number quantitative limitation that can load, it is impossible to carry out many to reactor pressure vessel
The detection at position, it is impossible to meet the requirement to reactor pressure vessel irradiation when following nuclear power station is lengthened the life；Irradiation monitoring pipe
During transport, when security requirement height, irradiation control sample test, radioactivity protection requires that high, cost height and cycle are long, the follow-up three wastes
Processing pressure is big；And the problem such as the irradiation damage degree that can not monitor reactor pressure vessel specific part, it is desirable to provide one
Kind of economy, environmental protection, safe efficient, the multiple position of reactor pressure vessel (including specific part) irradiation damage can be monitored in real time
Nuclear power plant reactor pressure vessel irradiation damage monitoring method and device.Its core concept is: at present, China is in-service,
The reactor pressure vessel steel building nuclear power station is manganese nickel molybdenum low-alloy steel material, and France's AFCEN trade mark is 16MND5, is similar to
U.S. ASME trade mark SA-508-III steel.And shown by experimentation: the resistivity of this material is during neutron irradiation
Rate of change presents preferable regularity, and has preferable dependency with the irradiation damage degree of this material.Therefore, can be by prison
Measured reaction core pressure vessel runs the situation of change of reactor pressure vessel steel resistivity during being on active service and analyzes acquisition reaction
The situation of change of core pressure vessel steel mechanical property, and then the irradiation damage degree of assessment reactor pressure vessel, be used for carrying out
The work such as the safety evaluation of the structural intergrity during reactor pressure vessel irradiation damage, biometry.
Embodiment one:
Fig. 1 shows the method step of a kind of real-time monitoring reactor pressure vessel irradiation damage:
S1, set up benchmark: record initial electrical resistivity ρ of reactor pressure vessel steel0；Concrete, " four leads method can be used
(also known as four-point method or four-end method) " record initial electrical resistivity ρ of reactor pressure vessel reactor core district steel0It is 30.3 μ Ω
Cm, it is possible to use other conventional method to record initial electrical resistivity ρ 0 of reactor pressure vessel.
S2, in real time monitoring: in nuclear power station properly functioning period, obtain the described reactor pressure of certain particular point in time in real time
Electricalresistivityρ after force container steel irradiation damage；Concrete, " four leads method (also known as four-point method or four-end method) " can be used to survey
After reactor pressure vessel irradiation damage real time resistance rate ρ of same position be 36.9 μ Ω cm, it is possible to use other conventional
Method records the electricalresistivityρ after reactor pressure vessel steel irradiation damage.
S3, analytical calculation: first based on described initial electrical resistivity ρ0With the described reactor pressure vessel monitoring gained in real time
Electricalresistivityρ after steel irradiation damage calculates the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage；Tool
Body, calculate the rate of change δ (ρ) of resistivity after described reactor pressure vessel reactor core district steel irradiation damage according to formula (1), its
Described in formula (1) be:
δ (ρ)=(ρ-ρ0)/ρ0 (1)
After calculating the irradiation damage of described reactor pressure vessel steel core region, the rate of change δ (ρ) of resistivity is
21.78%.
Further, obtain described reactor pressure vessel steel further according to the rate of change δ (ρ) of resistivity after described damage to exist
The rate of change of the macro-mechanical property parameter in irradiation damage；Described macro-mechanical property parameter is real-time tensile strength Rm, real
Time yield strength Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one, it is corresponding
Rate of change be respectively real-time tensile strength RmRate of change δ (Rm), real-time yield strength Rp0.2Rate of change δ (Rp0.2), in real time upper flat
Platform energy USE rate of change δ (USE) and in real time nil ductility temperature RTNDTRate of change δ (RTNDT)；
Concrete, calculate described real-time tensile strength R respectively according to described formula (2-1)-(2-4)mRate of change δ (Rm), real
Time yield strength Rp0.2Rate of change δ (Rp0.2), real-time upper mounting plate energy USE rate of change δ (USE) and real-time nil ductility transition temperature
Degree RTNDTRate of change δ (RTNDTAt least one in), described formula (2-1)-(2-4) is respectively as follows:
δ(Rm)=λ1·δ(ρ) (2-1)
δ(Rp0.2)=λ2·δ(ρ) (2-2)
δ (USE)=λ3·δ(ρ) (2-3)
δ(RTNDT)=λ4·δ(ρ) (2-4)
Wherein: λ1, λ2, λ3And λ4Being proportionality coefficient, usual span is 0.85-1.35, and concrete value can root
According to reactor pressure vessel steel original state Microstructure characteristics (as grain size, Types of Dislocations, quantity, second phase distribution spy
Point etc.) and the combined factors such as nuclear power station run duration pile neutron irradiation field power spectrum determine, for specific nuclear power station with
Reactor pressure vessel, above-mentioned λ1, λ2, λ3And λ4Also can be the most true by traditional irradiation control sample mechanical property test
Determine or revise.
In the present embodiment, λ1, λ2, λ3And λ4Value is respectively: 0.95,1.35,1.02,0.85, thus calculate reality
Time tensile strength RmRate of change δ (Rm) be 20.69%, real-time yield strength Rp0.2Rate of change δ (Rp0.2) be 29.40%, in real time on
Platform energy USE rate of change δ (USE) is 22.22%, real-time nil ductility temperature RTNDTRate of change δ (RTNDT) it is
18.51%.
Real-time tensile strength R is calculated further according to formula (3-1)-(3-4)m, real-time yield strength Rp0.2, in real time
Upper mounting plate energy USE and in real time nil ductility temperature RTNDT, described formula (3-1)-(3-4) is respectively as follows:
δ(Rm)=[Rm-(Rm)Initially]/(Rm)Initially (3-1)
δ(Rp0.2)=[Rp0.2-(Rp0.2)Initially]/(Rp0.2)Initially (3-2)
δ (USE)=[USE-(USE)Initially]/(USE)Initially (3-3)
δ(RTNDT)=[RTNDT-(RTNDT)Initially]/(RTNDT)Initially (3-4)
Wherein: (Rm)InitiallyTensile strength for reactor pressure vessel steel original state；
(Rp0.2)InitiallyYield strength for reactor pressure vessel steel original state；
(USE)InitiallyUpper mounting plate energy for reactor pressure vessel steel original state；
(RTNDT)InitiallyNil ductility temperature for reactor pressure vessel steel original state；
Above-mentioned (Rm)Initially,(Rp0.2)Initially、(USE)InitiallyAnd (RTNDT)InitiallyAll can be from reactor pressure vessel equipment manufacturing
In the equipment complete report provided, inquiry obtains.In the present embodiment, obtain above-mentioned (R through inquirym)Initially,(Rp0.2)Initially、(USE)Initially
And (RTNDT)InitiallyIt is respectively 591MPa, 483MPa, 335J and 241K.
Concrete calculating process is:
Rm=(Rm)Initially×[1+δ(Rm)]=591 × (1+20.69%)=713MPa
RP0.2=(RP0.2)Initially×[1+δ(RP0.2)]=483 × (1+29.40%)=625MPa
USE=(USE)Initially× [1-δ (USE)]=335 × (1-22.22%)=261J
Note: after reactor pressure vessel steel neutron irradiation damage, its upper mounting plate energy reduces, and its numerical value correspondence reduces, because of
It is [1-δ (USE)] at this this, rather than [1+ δ (USE)].
RTNDT=(RTNDT)Initially×[1+δ(RTNDT)]=241 × (1+18.51%)=285K
Note: for ease of calculating, nil ductility temperature RTNDTUnit use absolute temperature units, rather than generally use
Centigrade thermic unit, conversion relation between the two is: absolute temperature (K)=273+ Celsius temperature (DEG C)；
S4, security evaluation: assess the irradiation of described reactor pressure vessel according to described macro-mechanical property Parameter analysis
Injury tolerance.
For verifying the effectiveness of the method for the invention, take and there is identical irradiation damage degree (refer generally to have identical
Neutron irradiation accumulation fluence) traditional reactor pressure vessel irradiation control sample carry out destructive mechanical property test, survey
Examination obtains its tensile strength, yield strength, upper mounting plate energy and nil ductility temperature.Table 1 shows and calculates through the present invention
Draw and test each mechanical property parameters numerical value drawn through traditional reactor pressure vessel irradiation control sample.
Be can be seen that by table 1, it can be seen that use the method for the invention calculated mechanical property parameters numerical value with
Measured value is closely.This deviation value the most within the acceptable range, will not be to subsequent reactions core pressure vessel irradiation damage
Safety evaluation bring impact.
Table 1
Note:
(1) negative sign "-" represents negative value, and i.e. after irradiation, the upper mounting plate energy USE of reactor pressure vessel steel is to reduce；
(2) it is limited to the limitation of current means of testing, generally acknowledges that the most in the industry the test error of this value is generally at ± 5 DEG C
Within, individual cases are up to ± 10 DEG C.
Embodiment two:
See Fig. 2, it illustrates a kind of change by monitoring resistor rate and monitor reactor pressure vessel irradiation damage in real time
The device of wound, including:
Detector unit and assessment unit, described detector unit one end coupled reaction core pressure vessel, be used for detecting reaction
The resistivity of core pressure vessel steel, the other end connects described assessment unit；Described assessment unit for according to described in detect
The resistivity of reactor pressure vessel steel calculates the rate of change of resistivity after described reactor pressure vessel steel irradiation damage,
And calculate reactor pressure vessel steel according to the rate of change of resistivity after described reactor pressure vessel steel irradiation damage and exist
Macro-mechanical property parameter in irradiation damage, and according to described macro-mechanical property parameter to described reactor pressure vessel
Irradiation damage degree carries out security evaluation.
Preferably, the resistance of described reactor pressure vessel steel is: after described reactor pressure vessel is installed and put in place,
And before nuclear power station first fuel loading runs, initial electrical resistivity ρ of the described reactor pressure vessel steel recorded0, and at core
Power station properly functioning period, the electricity after the described reactor pressure vessel steel irradiation damage of certain particular point in time recorded in real time
Resistance rate ρ.
Preferably, described assessment unit includes memory element, for storing the reactor pressure that described detector unit detects
The resistance of force container steel；Computing unit, the resistance calculations of the reactor pressure vessel steel for detecting described in basis draws institute
State the rate of change of resistivity after reactor pressure vessel steel irradiation damage, and according to described reactor pressure vessel steel irradiation damage
The rate of change of rear resistivity calculates reactor pressure vessel steel macro-mechanical property parameter in irradiation damage；And sentence
Disconnected unit, for according to described in the reactor pressure vessel steel that the calculates macro-mechanical property parameter in irradiation damage come
The irradiation damage degree of described reactor pressure vessel is carried out security evaluation.
Preferably, the resistance calculations of the reactor pressure vessel steel detected described in described basis draws described reactor pressure
The rate of change δ (ρ) of resistivity after force container steel irradiation damage, then step by step calculation draws real-time tensile strength RmRate of change δ (Rm)、
Yield strength R in real timep0.2Rate of change δ (Rp0.2), real-time upper mounting plate energy USE rate of change δ (USE) and real-time nil ductility transition
Temperature RTNDTRate of change δ (RTNDTAt least one in), and tensile strength R in real timem, real-time yield strength Rp0.2, in real time upper flat
Platform energy USE and in real time nil ductility temperature RTNDTIn at least one, its calculate process with embodiment one.
Preferably, arrange pre-conditioned in described judging unit, by described real-time tensile strength Rm, real-time yield strength
Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one as analyze input parameter
Input described judging unit, when described analyze input parameter numerical value meet described pre-conditioned time, described judging unit sends
Early warning.
Preferably, described device also includes display unit, and described display unit connects described assessment unit, is used for showing institute
State macro-mechanical property parameter and the security evaluation result to described reactor pressure vessel irradiation damage degree.
It should be noted that the invention described above embodiment sequence number is just to describing, do not represent the quality of embodiment.
In sum, the method and apparatus that the invention provides a kind of real-time monitoring reactor pressure vessel irradiation damage,
By recording the initial electrical resistivity of reactor pressure vessel steel and obtaining the described reactor pressure of certain particular point in time in real time
Resistivity after container steel irradiation damage calculates the rate of change of resistivity after described reactor pressure vessel steel irradiation damage；And
Described reactor pressure vessel steel macroforce in irradiation damage is obtained according to the rate of change of resistivity after described irradiation damage
Learn performance parameter；And then the irradiation damage of described reactor pressure vessel is assessed according to described macro-mechanical property Parameter analysis
Degree.
One of ordinary skill in the art will appreciate that all or part of step realizing above-described embodiment can pass through hardware
Completing, it is also possible to instruct relevant hardware by program and complete, described program can be stored in a kind of computer-readable
In storage medium, storage medium mentioned above can be read only memory, disk or CD etc..
The foregoing is only presently preferred embodiments of the present invention, not in order to limit the present invention, all spirit in the present invention and
Within principle, any modification, equivalent substitution and improvement etc. made, should be included within the scope of the present invention.
Claims (16)
1. the method monitoring reactor pressure vessel irradiation damage, it is characterised in that comprise the steps:
S1, set up benchmark: record initial electrical resistivity ρ of reactor pressure vessel steel0；
S2, in real time monitoring: in nuclear power station properly functioning period, obtain the described reactor pressure vessel steel of random time point in real time
Electricalresistivityρ after irradiation damage；
S3, analytical calculation: based on described initial electrical resistivity ρ0Damage with the described reactor pressure vessel steel irradiation of monitoring gained in real time
Electricalresistivityρ after wound calculates the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage；And according to described
After damage, the rate of change δ (ρ) of resistivity obtains described reactor pressure vessel steel macro-mechanical property ginseng in irradiation damage
Number；
S4, security evaluation: assess the irradiation damage of described reactor pressure vessel according to described macro-mechanical property Parameter analysis
Degree.
2. the method for claim 1, it is characterised in that described macro-mechanical property parameter is real-time tensile strength Rm, real
Time yield strength Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one.
3. the method for claim 1, it is characterised in that in step S1, described initial electrical resistivity
ρ0The process that records be: after described reactor pressure vessel is installed and put in place, and run it at nuclear power station first fuel loading
Before, record initial electrical resistivity ρ of described reactor pressure vessel steel0。
4. method as claimed in claim 3, it is characterised in that in step S1, record during nuclear power station heat is tried described initially
Electricalresistivityρ0。
5. method as claimed in claim 2, it is characterised in that comprise the steps: in step S3
S3a, calculate the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage:
The rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage is calculated according to formula (1), wherein said
Formula (1) is:
δ (ρ)=(ρ-ρ0)/ρ0 (1)
S3b, foundation formula (2-1)-(2-4) calculate described reactor pressure vessel steel real-time tensile strength R in irradiation damagem
Rate of change δ (Rm), real-time yield strength Rp0.2Rate of change δ (Rp0.2), real-time upper mounting plate energy USE rate of change δ (USE) and real
Time nil ductility temperature RTNDTRate of change δ (RTNDTAt least one in), wherein said formula (2-1)-(2-4) is respectively as follows:
δ(Rm)=λ1·δ(ρ) (2-1)
δ(Rp0.2)=λ2·δ(ρ) (2-2)
δ (USE)=λ3·δ(ρ) (2-3)
δ(RTNDT)=λ4·δ(ρ) (2-4)
Wherein: λ1, λ2, λ3And λ4Being proportionality coefficient, usual span is 0.85-1.35, and its value influence factor include:
The Microstructure characteristics of reactor pressure vessel steel original state and the energy of nuclear power station run duration pile neutron irradiation field
Spectrum；
S3c, foundation formula (3-1)-(3-4) calculate described reactor pressure vessel steel real-time tensile strength R in irradiation damagem、
Yield strength R in real timep0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one, wherein
Described formula (3-1)-(3-4) is respectively as follows:
δ(Rm)=[Rm-(Rm)Initially]/(Rm)Initially (3-1)
δ(Rp0.2)=[Rp0.2-(Rp0.2)Initially]/(Rp0.2)Initially (3-2)
δ (USE)=[USE-(USE)Initially]/(USE)Initially (3-3)
δ(RTNDT)=[RTNDT-(RTNDT)Initially]/(RTNDT)Initially (3-4)
Wherein: (Rm)InitiallyTensile strength for reactor pressure vessel steel original state；
(Rp0.2)InitiallyYield strength for reactor pressure vessel steel original state；
(USE)InitiallyUpper mounting plate energy for reactor pressure vessel steel original state；
(RTNDT)InitiallyNil ductility temperature for reactor pressure vessel steel original state；
Above-mentioned (Rm)Initially、(Rp0.2)Initially、(USE)InitiallyAnd (RTNDT)InitiallyAll can provide from reactor pressure vessel equipment manufacturing
Equipment complete report in inquiry obtain.
6. method as claimed in claim 5, it is characterised in that for specific nuclear power station and reactor pressure vessel, above-mentioned
λ1, λ2, λ3And λ4Also can be determined by traditional irradiation control sample mechanical property test or be revised.
7. method as claimed in claim 5, it is characterised in that the security evaluation process in step S4 is: by described the most anti-
Tensile strength Rm, real-time yield strength Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least
The irradiation damage degree of described reactor pressure vessel, as analyzing input parameter, is carried out by one according to described input parameter of analyzing
Security evaluation.
8. method as claimed in claim 7, it is characterised in that described according to described input parameter of analyzing to described reactor pressure
The irradiation damage degree of force container carries out the step of security evaluation and includes: arrange pre-conditioned, when the described number analyzing input parameter
Value meet described pre-conditioned time, send early warning.
9. the device monitoring reactor pressure vessel irradiation damage, it is characterised in that comprising: detector unit and assessment
Unit, described detector unit one end coupled reaction core pressure vessel, for detecting the resistivity of reactor pressure vessel steel, another
End connects described assessment unit；The resistrivity meter of the described assessment unit reactor pressure vessel steel for detecting described in basis
Calculate and draw the rate of change of resistivity after described reactor pressure vessel steel irradiation damage, and according to described reactor pressure vessel steel
After irradiation damage, the rate of change of resistivity calculates described reactor pressure vessel steel macromechanics in irradiation damage
Energy parameter, and carry out commenting safely to the irradiation damage degree of described reactor pressure vessel according to described macro-mechanical property parameter
Estimate.
10. device as claimed in claim 9, it is characterised in that the resistance of described reactor pressure vessel steel is: described instead
After answering core pressure vessel installation to put in place, and before nuclear power station first fuel loading runs, the described reactor pressure vessel recorded
Initial electrical resistivity ρ of steel0, and in nuclear power station properly functioning period, the described reaction of certain particular point in time recorded in real time
Electricalresistivityρ after core pressure vessel steel irradiation damage.
11. devices as claimed in claim 10, it is characterised in that described assessment unit includes memory element, is used for storing institute
State the resistance of the reactor pressure vessel steel that detector unit detects；Computing unit, for the reactor detected described in basis
The resistance calculations of pressure vessel steel draws the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage, and root
Calculate reactor pressure vessel steel according to the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage to exist
Macro-mechanical property parameter in irradiation damage；And judging unit, hold for the reactor pressure calculated described in basis
Device steel macro-mechanical property parameter in irradiation damage carries out safety to the irradiation damage degree of described reactor pressure vessel
Assessment.
12. devices as claimed in claim 11, it is characterised in that the reactor pressure vessel steel detected described in described basis
Resistance calculations draw described reactor pressure vessel steel irradiation damage after the process of rate of change of resistivity be: according to formula
(1) calculating the rate of change δ (ρ) of resistivity after described reactor pressure vessel steel irradiation damage, wherein said formula (1) is: δ
(ρ)=(ρ-ρ0)/ρ0 (1)。
13. devices as claimed in claim 12, it is characterised in that described macro-mechanical property parameter is real-time tensile strength Rm、
Yield strength R in real timep0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one.
14. devices as claimed in claim 13, it is characterised in that described according to described reactor pressure vessel steel irradiation damage
The rate of change of rear resistivity calculates the process of reactor pressure vessel steel macro-mechanical property parameter in irradiation damage
For:
Described reactor pressure vessel steel real-time tensile strength R in irradiation damage is calculated according to formula (2-1)-(2-4)mChange
Rate δ (Rm), real-time yield strength Rp0.2Rate of change δ (Rp0.2), real-time upper mounting plate energy USE rate of change δ (USE) and real-time nothing
Ductility transition temperature RTNDTRate of change δ (RTNDTAt least one in), wherein said formula (2-1)-(2-4) is respectively as follows:
δ(Rm)=λ1·δ(ρ) (2-1)
δ(Rp0.2)=λ2·δ(ρ) (2-2)
δ (USE)=λ3·δ(ρ) (2-3)
δ(RTNDT)=λ4·δ(ρ) (2-4)
Wherein: λ1, λ2, λ3And λ4Being proportionality coefficient, usual span is 0.85-1.35, and its value influence factor include:
The Microstructure characteristics of reactor pressure vessel steel original state and the energy of nuclear power station run duration pile neutron irradiation field
Spectrum；
The described reactor pressure vessel steel real-time tensile strength R in irradiation damage is calculated again according to formula (3-1)-(3-4)m、
Yield strength R in real timep0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn at least one, wherein
Described formula (3-1)-(3-4) is respectively as follows:
δ(Rm)=[Rm-(Rm)Initially]/(Rm)Initially (3-1)
δ(Rp0.2)=[Rp0.2-(Rp0.2)Initially]/(Rp0.2)Initially (3-2)
δ (USE)=[USE-(USE)Initially]/(USE)Initially (3-3)
δ(RTNDT)=[RTNDT-(RTNDT)Initially]/(RTNDT)Initially (3-4)
Wherein: (Rm)InitiallyTensile strength for reactor pressure vessel steel original state；
(Rp0.2)InitiallyYield strength for reactor pressure vessel steel original state；
(USE)InitiallyUpper mounting plate energy for reactor pressure vessel steel original state；
(RTNDT)InitiallyNil ductility temperature for reactor pressure vessel steel original state；
Above-mentioned (Rm)Initially,(Rp0.2)Initially、(USE)InitiallyAnd (RTNDT)InitiallyAll can provide from reactor pressure vessel equipment manufacturing
Equipment complete report in inquiry obtain.
15. devices as claimed in claim 14, it is characterised in that arrange pre-conditioned in described judging unit, by described
Tensile strength R in real timem, real-time yield strength Rp0.2, real-time upper mounting plate energy USE and real-time nil ductility temperature RTNDTIn
At least one as analyze input parameter input described judging unit, when described analyze input parameter numerical value meet described pre-
If during condition, described judging unit sends early warning.
16. devices as claimed in claim 9, it is characterised in that also include display unit, described display unit connects institute's commentary
Estimate unit, for showing described macro-mechanical property parameter and the safety of described reactor pressure vessel irradiation damage degree being commented
Estimate result.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610614794.XA CN106128528B (en) | 2016-07-28 | 2016-07-28 | A kind of method and apparatus for monitoring nuclear power plant reactor pressure vessel irradiation damage |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610614794.XA CN106128528B (en) | 2016-07-28 | 2016-07-28 | A kind of method and apparatus for monitoring nuclear power plant reactor pressure vessel irradiation damage |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106128528A true CN106128528A (en) | 2016-11-16 |
| CN106128528B CN106128528B (en) | 2017-05-31 |
Family
ID=57254301
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610614794.XA Active CN106128528B (en) | 2016-07-28 | 2016-07-28 | A kind of method and apparatus for monitoring nuclear power plant reactor pressure vessel irradiation damage |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106128528B (en) |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106710648A (en) * | 2016-12-16 | 2017-05-24 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel irradiation damage monitoring method |
| CN107123451A (en) * | 2017-05-09 | 2017-09-01 | 中广核工程有限公司 | The method of nuclear power station monitoring and evaluation reactor pressure vessel steel irradiation damage |
| CN107123452A (en) * | 2017-05-09 | 2017-09-01 | 中广核工程有限公司 | The method of nuclear power station nondestructive evaluation reactor pressure vessel irradiation damage |
| CN107146646A (en) * | 2017-05-09 | 2017-09-08 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel steel irradiation damage nondestructive evaluation method |
| CN107358983A (en) * | 2017-07-20 | 2017-11-17 | 深圳中广核工程设计有限公司 | The method for monitoring nuclear power plant reactor pressure vessel neutron irradiation damage fluence |
| CN107481776A (en) * | 2017-07-27 | 2017-12-15 | 深圳中广核工程设计有限公司 | The method and apparatus for assessing nuclear power plant reactor pressure vessel neutron irradiation damage |
| CN108277338A (en) * | 2018-01-12 | 2018-07-13 | 中广核工程有限公司 | It is a kind of to prepare the system and method for having negative resistance rate current coefficient material |
| WO2018205607A1 (en) * | 2017-05-09 | 2018-11-15 | 中广核工程有限公司 | Non-destructive assessment method for radiation damage of reactor pressure vessel in nuclear power plant |
| WO2019104510A1 (en) * | 2017-11-29 | 2019-06-06 | 中广核工程有限公司 | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH09159652A (en) * | 1995-12-12 | 1997-06-20 | Ishikawajima Harima Heavy Ind Co Ltd | Method for foreseeing danger of containing structure |
| JP2000131486A (en) * | 1998-10-26 | 2000-05-12 | Mitsubishi Heavy Ind Ltd | Degradation degree sensing method |
| CN101305276A (en) * | 2005-11-14 | 2008-11-12 | Abb公司 | Method and apparatus for estimating a mechanical property |
-
2016
- 2016-07-28 CN CN201610614794.XA patent/CN106128528B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH09159652A (en) * | 1995-12-12 | 1997-06-20 | Ishikawajima Harima Heavy Ind Co Ltd | Method for foreseeing danger of containing structure |
| JP2000131486A (en) * | 1998-10-26 | 2000-05-12 | Mitsubishi Heavy Ind Ltd | Degradation degree sensing method |
| CN101305276A (en) * | 2005-11-14 | 2008-11-12 | Abb公司 | Method and apparatus for estimating a mechanical property |
Non-Patent Citations (2)
| Title |
|---|
| B.ACOSTA ET AL: "A preliminary evaluation of irradiation damage in model alloys by electric properties based techniques", 《INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING 》 * |
| RISTO ILOLA, ET AL: "On irradiation embrittlement and recovery annealing mechanisms of Cr-Mo-V type pressure vessel steels", 《JOURNAL OF NUCLEAR MATERIALS》 * |
Cited By (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106710648A (en) * | 2016-12-16 | 2017-05-24 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel irradiation damage monitoring method |
| CN106710648B (en) * | 2016-12-16 | 2018-03-06 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel irradiation damage monitoring method |
| CN107123451B (en) * | 2017-05-09 | 2019-02-01 | 深圳中广核工程设计有限公司 | The method of nuclear power station monitoring and evaluation reactor pressure vessel steel irradiation damage |
| CN107123451A (en) * | 2017-05-09 | 2017-09-01 | 中广核工程有限公司 | The method of nuclear power station monitoring and evaluation reactor pressure vessel steel irradiation damage |
| CN107123452A (en) * | 2017-05-09 | 2017-09-01 | 中广核工程有限公司 | The method of nuclear power station nondestructive evaluation reactor pressure vessel irradiation damage |
| CN107146646A (en) * | 2017-05-09 | 2017-09-08 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel steel irradiation damage nondestructive evaluation method |
| GB2577425B (en) * | 2017-05-09 | 2022-08-17 | China Nuclear Power Eng Co Ltd | Non-destructive assessment method for radiation damage of reactor pressure vessel in nuclear power plant |
| GB2577425A (en) * | 2017-05-09 | 2020-03-25 | China Nuclear Power Eng Co Ltd | Non-destructive assessment method for radiation damage of reactor pressure vessel in nuclear power plant |
| WO2018205607A1 (en) * | 2017-05-09 | 2018-11-15 | 中广核工程有限公司 | Non-destructive assessment method for radiation damage of reactor pressure vessel in nuclear power plant |
| CN107146646B (en) * | 2017-05-09 | 2018-12-04 | 深圳中广核工程设计有限公司 | Nuclear power plant reactor pressure vessel steel irradiation damage nondestructive evaluation method |
| CN107358983A (en) * | 2017-07-20 | 2017-11-17 | 深圳中广核工程设计有限公司 | The method for monitoring nuclear power plant reactor pressure vessel neutron irradiation damage fluence |
| CN107358983B (en) * | 2017-07-20 | 2019-08-20 | 深圳中广核工程设计有限公司 | The method for monitoring nuclear power plant reactor pressure vessel neutron irradiation damage fluence |
| CN107481776A (en) * | 2017-07-27 | 2017-12-15 | 深圳中广核工程设计有限公司 | The method and apparatus for assessing nuclear power plant reactor pressure vessel neutron irradiation damage |
| WO2019104510A1 (en) * | 2017-11-29 | 2019-06-06 | 中广核工程有限公司 | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel |
| GB2583292A (en) * | 2017-11-29 | 2020-10-21 | China Nuclear Power Eng Company Ltd | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel |
| GB2583292B (en) * | 2017-11-29 | 2023-03-08 | China Nuclear Power Eng Company Ltd | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel |
| CN108277338A (en) * | 2018-01-12 | 2018-07-13 | 中广核工程有限公司 | It is a kind of to prepare the system and method for having negative resistance rate current coefficient material |
| CN108277338B (en) * | 2018-01-12 | 2020-04-28 | 深圳中广核工程设计有限公司 | System and method for preparing negative resistivity current coefficient material |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106128528B (en) | 2017-05-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106128528A (en) | A kind of method and apparatus monitoring nuclear power plant reactor pressure vessel irradiation damage | |
| CN110349686B (en) | Method for monitoring irradiation embrittlement of reactor pressure vessel of nuclear power station | |
| CN107123451B (en) | The method of nuclear power station monitoring and evaluation reactor pressure vessel steel irradiation damage | |
| CN101939795B (en) | Method of determining the value of a parameter representative of the operability of a nuclear reactor, determining system, computer program and corresponding medium | |
| CN107358983B (en) | The method for monitoring nuclear power plant reactor pressure vessel neutron irradiation damage fluence | |
| CN107146646B (en) | Nuclear power plant reactor pressure vessel steel irradiation damage nondestructive evaluation method | |
| CN207096165U (en) | Mixed gas concentration on-line measurement device | |
| CN109817357B (en) | Method and device for evaluating radiation damage of reactor pressure vessel based on magnetization work | |
| CN107123452B (en) | The method of nuclear power station nondestructive evaluation reactor pressure vessel irradiation damage | |
| CN204855152U (en) | Online calibration equipment of portable safety valve | |
| CN104282348A (en) | Method for detecting nondestructive on-line life of pressure vessel steel | |
| Coleman et al. | Evaluation of Zircaloy-2 pressure tubes from NPD | |
| WO2019104510A1 (en) | Method and device for evaluating degree of neutron irradiation embrittlement of nuclear power plant reactor pressure vessel | |
| CN107481776A (en) | The method and apparatus for assessing nuclear power plant reactor pressure vessel neutron irradiation damage | |
| Kanto et al. | Recent Japanese research activities on probabilistic fracture mechanics for pressure vessel and piping of nuclear power plant | |
| Cho et al. | Probabilistic Assessment of CANDU Reactor Core for Risk of Pressure Tube Failure due to Presence of In-Service Flaws | |
| Bergmann et al. | OUT-OF-PILE VERIFICATION OF TRITON11™ BWR FUEL | |
| Kaliatka et al. | BEST ESTIMATE ANALYSIS OF PROCESSES IN RBMK FUEL RODS DURING OPERATION CYCLE | |
| CN106710648A (en) | Nuclear power plant reactor pressure vessel irradiation damage monitoring method | |
| Montgomery | Researching the Effects of Long-Term Dry Storage on Commercial Spent Nuclear Fuel | |
| Hongchao et al. | Tests of the Package for the Transport of Natural Uranium Hexafluoride | |
| Yada et al. | Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept | |
| Ferng | Predicting growth rate of wall thinning for severely degraded SG tubes using a statistical methodology | |
| Choi et al. | Optimization for the prediction using results of gap measurements between fuel channels and liss nozzles in phwr | |
| Xiaohui | Analysis and Research on Diagnosis Methods of AFA 3G Fuel Assembly Leakage |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |