CN106571168A - Real-time monitoring method and system for fast neutron fluence rate of reactor pressure vessel - Google Patents
Real-time monitoring method and system for fast neutron fluence rate of reactor pressure vessel Download PDFInfo
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- CN106571168A CN106571168A CN201510655339.XA CN201510655339A CN106571168A CN 106571168 A CN106571168 A CN 106571168A CN 201510655339 A CN201510655339 A CN 201510655339A CN 106571168 A CN106571168 A CN 106571168A
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention provides a real-time monitoring method and system for the fast neutron fluence rate of a reactor pressure vessel. A reactor comprises a reactor core monitoring system used for monitoring operating parameters of a reactor core in the pressure vessel in real time. The real-time monitoring system comprises a data receive unit, a neutron fluence rate calculating unit and a display unit. The data receive unit is configured to receive real-time operating parameter data of the reactor core from the reactor core monitoring system with specified monitoring frequency. The neutron fluence rate calculating unit is configured to calculate the fast neutron fluence rate of the pressure vessel at least based on the received real-time operating parameter data. The display unit is configured to visually output the calculated fast neutron fluence rate.
Description
Technical field
Embodiments of the invention are usually related to nuclear power plant's reactor core monitoring and pressure vessel irradiation prison
Superintend and direct field, and especially, be related to it is a kind of for real-time monitoring reactor pressure vessel it is fast in
The method and system of sub- fluence rate.
Background technology
Npp safety, the core component of aging and management of lengthening the life --- reactor pressure vessel is
Dispose nuclear reactor and bear the hermetic container of its huge operating pressure, also referred to as reactor vessel,
It is the key equipment in pressurized-water reactor nuclear power plant, with manufacturing technology standard is high, difficulty is big and the cycle
Long the features such as, and be non-exchange equipment, it is necessary to assure which is exhausted in nuclear power station lifetime
To safe and reliable, it is desirable under various accidental conditions, operating condition of test and hypothetical accident operating mode
The integrity of its structure is kept, not the non-ductile rupture failure and radioactive substance of generation container
Leakage.Its major function is as follows：(1) nuclear fuel assembly and in-pile component are loaded, to reactor core
Act on radiation shield；(2) control rod base and its drive mechanism are installed on top cover；
(3) seal primary Ioops coolant and maintain its pressure, be the important portion on coolant pressure border
Point；(4) there is the function of preventing fission product excessive after the breakage of fuel original paper.Pressure vessel sets
Meter, manufacture, in-service surveillance must comply with strict criterion, its integrity under arms in the phase in longevity
It is most important to reactor safety.It and primary coolant circuit pipe collectively constitute the pressure of pressure coolant
Border, is one of second barrier for preventing radioactive substance from escaping, in spy in safety
Different status, is defined as " non-exchange sensitive kind equipment " in the longevity period management in power station.
Reactor pressure vessel is washed away and corrodes in high temperature, high-pressure fluid, and it is strong in
Run under the mal-conditions such as sub- irradiation, reactor pressure vessel is caused material mechanical special by irradiation
Property change, i.e. radiation embrittlement problem be one of the principal element for affecting its phase in longevity.Pressure vessel
Life-span depends primarily on irradiation effect of fast neutron of the energy higher than 0.1MeV to which, and energy is high
Then material radiation damage embrittlement is played a leading role in the fast neutron of 1MeV.As power plant's life-span
Assessment and the vital parameter lengthened the life, the neutron fluence of pressure vessel are to determine pressure vessel
Brittle degree and a strong foundation of evaluation pressure vessel high pressure thermal shock.Therefore, for pressure
The supervision of force container fast neutron fluence, plays vital to nuclear power plant's economy and safety
Effect.
For the irradiation of pressure vessel in current engineering, typically there are two kinds of methods, one is
When nuclear power station Radiation Shielding Re design is carried out, by the calculating to pressure vessel Fast neutron flux,
And integration draws pressure vessel longevity phase Fast neutron flux, it is ensured that what nuclear power plant was guarded in design
Meet above-mentioned anti-radiation performance；Another is to utilize irradiation monitoring pipe, will pressure vessel mother
Material and weld material make sample, load stainless steel tube, and the height along reactor core active section is fixed on
On the outside of the cradle cylinder body of in-pile component, being extracted out within the phase in reactor longevity according to plan carries out performance test
And analysis, to supervise the part with material change after indicating pressure container irradiation.Both approaches
Poor real-time or big calculation error are there is, truly directly can not be reflected very much
The irradiation situation of pressure vessel.
The content of the invention
In order to overcome at least one in above and other problem and defect of prior art presence,
Propose the present invention.
According to an aspect of the present invention, it is proposed that a kind of pressure vessel of reactor it is fast in
The real-time monitoring system of sub- fluence rate, the reactor are included in monitoring pressure in real time container
Reactor core operational factor reactor core monitoring system, the real-time monitoring system includes：Data connect
Unit is received, is configured to receive the reality of reactor core with specified monitoring frequency from reactor core monitoring system
When operational parameter data；Neutron fluence rate computing unit, is configured at least based on receiving
Real time execution supplemental characteristic calculate pressure vessel Fast neutron flux；And display unit,
It is configured to for the Fast neutron flux for calculating to carry out visualization output.
Preferably, in above-mentioned real-time monitoring system, the real time execution supplemental characteristic can be wrapped
Include the realtime power distribution and the real-time combustion of real-time nucleic composition information and nuclear fuel assembly of reactor core
Consumption information.
Preferably, in above-mentioned real-time monitoring system, neutron fluence rate computing unit can include
Module is transported, this transports module and is configured to based on neutron-transport equation from by the real time execution
The fission neutron source strength and fission spectrum of the reactor core that supplemental characteristic is obtained calculates fast neutron note
Dose rate.
Preferably, in above-mentioned real-time monitoring system, neutron fluence rate computing unit can be matched somebody with somebody
It is set to and fission neutron source strength is obtained based on expressions below：
Nf=CPvN
Wherein：
Nf is fission neutron source normalization factor, and unit is 1/ (cm3·s)；
C be the Energy Conversion factor, C=6.24146 × 1012MeV/J；
Power densities of the Pv for nuclear fuel assembly, unit is W/cm；
N is the corresponding fission neutron number of release unit fission energy, N=v/E；
V is the average neutron number that fission is produced every time；And
E is the average energy of fission release every time, and unit is MeV.
Preferably, in above-mentioned real-time monitoring system, fission spectrum can be based on each
What the nucleic fission fraction under the average v values of combustible component and different burn-up levels was obtained
Mixing fission spectrum.
Preferably, in above-mentioned real-time monitoring system, transport module and may be configured to discrete
Vertical mark method calculates Fast neutron flux.
Preferably, above-mentioned real-time monitoring system can also include the base for being configured to receive reactor
The input block of this parameter, neutron fluence rate computing unit can be further configured to be based on and connect
The basic parameter for receiving and real time execution supplemental characteristic calculate Fast neutron flux.
Preferably, above-mentioned real-time monitoring system can also include being configured to be set and controlled in real time
The time stepping control unit of the monitoring frequency of monitoring system.
Preferably, above-mentioned real-time monitoring system can also include analysis and alarm unit, the analysis
It is configured to be performed in operations described below according to the Fast neutron flux for calculating with alarm unit
One or more：Analysis nominal situation；The exceeded warning of fluence rate；With fluence rate reason for Exceeding point
Analysis.
According to another aspect of the present invention, there is provided a kind of pressure for real-time monitoring reactor
The method of the Fast neutron flux of force container, the reactor are included for monitoring pressure in real time container
The reactor core monitoring system of the operational factor of interior reactor core, the method comprise the steps：To specify
Monitoring frequency from reactor core monitoring system receive reactor core real time execution supplemental characteristic；At least it is based on
The real time execution supplemental characteristic for receiving calculates the Fast neutron flux of pressure vessel；And will meter
The Fast neutron flux for calculating carries out visualization output.
Preferably, in the above-mentioned methods, the real time execution supplemental characteristic can include reactor core
Realtime power is distributed the real-time burnup information with real-time nucleic composition information and nuclear fuel assembly.
Preferably, in the above-mentioned methods, the step of calculating the Fast neutron flux of pressure vessel can
To include based on neutron-transport equation from the reactor core obtained by the real time execution supplemental characteristic
Fission neutron source strength and fission spectrum calculate Fast neutron flux.
Preferably, in the above-mentioned methods, fission neutron source strength can be obtained based on expressions below：
Nf=CPvN
Wherein：
Nf is fission neutron source normalization factor, and unit is 1/ (cm3·s)；
C be the Energy Conversion factor, C=6.24146 × 1012MeV/J；
Power densities of the Pv for nuclear fuel assembly, unit is W/cm；
N is the corresponding fission neutron number of release unit fission energy, N=v/E；
V is the average neutron number that fission is produced every time；And
E is the average energy of fission release every time, and unit is MeV.
Preferably, in the above-mentioned methods, can be by the average v values based on each combustible component
The mixing fission spectrum conduct obtained with the nucleic fission fraction under different burn-up levels
Fission spectrum.
Preferably, in the above-mentioned methods, the step of calculating the Fast neutron flux of pressure vessel can
To include calculating Fast neutron flux with DISORT method.
Preferably, said method can also include the step of receiving the basic parameter of reactor, and
And can include the step of the Fast neutron flux of calculating pressure vessel basic based on what is received
Parameter and real time execution supplemental characteristic calculate Fast neutron flux.
Preferably, under said method can also include being performed according to the Fast neutron flux for calculating
State one or more in operation：Nominal situation is analyzed；The exceeded warning of neutron fluence rate；With in
Sub- fluence rate Cause Analysis on Excess.
By below with reference to accompanying drawing detailed description made for the present invention, other mesh of the present invention
And advantage will be evident that, and can help that complete understanding of the invention will be obtained.
Description of the drawings
The features and advantages of the present invention can be more clearly understood from by reference to accompanying drawing, accompanying drawing is
Schematically should not be construed as carrying out the present invention any restriction, in the accompanying drawings：
Fig. 1 is for real-time monitoring reactor according to one exemplary embodiment of the present invention
Pressure vessel Fast neutron flux method flow chart；And
Fig. 2 is for real-time monitoring reactor according to one exemplary embodiment of the present invention
Pressure vessel Fast neutron flux system block diagram.
Specific embodiment
Below in conjunction with accompanying drawing, embodiments of the invention are described in detail.In this explanation
In book, same or analogous part is indicated by same or similar drawing reference numeral.It is following with reference to attached
Explanation of the figure to the embodiments of the present invention is intended to the general plotting for illustrating the present invention, and should not
Limit when the one kind to the present invention is interpreted as.
Additionally, in the following detailed description, for purposes of illustration only, elaborating many specific thin
Save to provide the comprehensive understanding to embodiments of the invention.It should be apparent, however, that one or more realities
Apply example to be carried out in the case where there is no these details.In other cases, it is public
The construction and device known diagrammatically embodies to simplify accompanying drawing.
A total inventive concept of the invention, there is provided for real-time monitoring reactor
Pressure vessel Fast neutron flux method and system, wherein supervising from the reactor core of reactor
Examining system receives the real time execution supplemental characteristic of reactor core, and according at least to the real-time fortune for receiving
Line parameter data calculate the Fast neutron flux with output pressure container in real time, can be effectively
Raising carries out the efficiency and precision of irradiation to pressure vessel, safety to nuclear power plant and prolongs
Longevity has obvious gain effect.
In one exemplary embodiment, as shown in Figure 1, there is provided a kind of for prison in real time
The method for surveying the Fast neutron flux of the pressure vessel of reactor, the reactor are included for reality
When monitoring pressure container in reactor core operational factor reactor core monitoring system.The method is main
Comprise the steps：
Step S101：The real time execution supplemental characteristic of reactor core is received from reactor core monitoring system；Example
Such as, the reception of this data can be according to the demand of the irradiation of pressure vessel with specified
Monitoring frequency is carried out；
Step S102：Pressure vessel is calculated based on the real time execution supplemental characteristic for receiving at least
Fast neutron flux；And
Step S103：The Fast neutron flux that output is calculated；For example, can visualize defeated
Go out calculated Fast neutron flux, intuitively to reflect the real-time irradiation feelings of pressure vessel
Condition.
In another exemplary embodiment, a kind of pressure vessel of reactor is additionally provided
The real-time monitoring system of Fast neutron flux, the reactor include holding for monitoring pressure in real time
The reactor core monitoring system of the operational factor of the reactor core in device, the real-time monitoring system include：
Data receipt unit, is configured to connect from reactor core monitoring system with specified monitoring frequency
The real time execution supplemental characteristic of closing heap core；
Neutron fluence rate computing unit, is configured at least based on the real time execution ginseng for receiving
Number data calculate the Fast neutron flux of pressure vessel；With
Display unit, is configured to for the Fast neutron flux for calculating to carry out visualization output；
Preferably, display unit according to the result of calculation of neutron fluence rate computing unit by constantly real
Shi Gengxin.For example, result of calculation fitting can be become the Dynamic Announce of three-dimensional visualization,
Exported to user by human-computer interface system, and real-time statistics neutron fluence integral result.
In one example, the real-time monitoring system can also include being configured to receive reaction
The input block of the basic parameter of heap.The basic parameter of reactor include reactor material,
The changeless parameter such as geometry, this partial parameters when reactor is designed just it has been determined that
For example, including reactor core, in-pile component, pressure vessel etc. material composition, regional temperature,
Physical dimension etc..
In order to calculate the Fast neutron flux of reactor pressure vessel in real time, need to collect reactor core
Real time execution supplemental characteristic.The real time execution supplemental characteristic of reactor core can include the real-time work(of reactor core
Rate distribution and real-time nucleic composition information, the real-time burnup information of nuclear fuel assembly etc..For example,
Based on the basic parameter of reactor, the three-dimensional power point of reactor core can be obtained from reactor core monitoring system
Cloth.The real time execution parameter of reactor core can be changed in real time with the operation of power plant, and this part is joined
It is several, need to read by the real-time detection of reactor core monitoring system.Can from real time execution supplemental characteristic
Obtain or derive the fission neutron source strength and fission spectrum of reactor core.
Can include transporting module in neutron fluence rate computing unit, or above-mentioned parameter is defeated
Enter to transporting in module, this transports module and is configured to based on neutron-transport equation by fission neutron
Source strength and fission spectrum calculate Fast neutron flux, preferably obtain pressure vessel it is fast in
The distributed in three dimensions of sub- fluence rate.Neutron fluence rate computing unit can be directed to different energy areas
(mainly energy is more than 1MeV and the neutron more than 0.1MeV) is to reactor pressure vessel
Carry out fluence rate calculating.Due to calculative real-time, calculating method faster is typically chosen,
Such as DISORT method, carry out transporting calculating, it is ensured that the speed and precision of calculating.Neutron transport side
Journey and its method for solving, such as DISORT method, are known in the art, and here is no longer detailed
Description.
Exemplarily, fission neutron source strength can be obtained based on expressions below：
Nf=CPvN
Wherein：
Nf is the fission neutron source normalization factor for characterizing source strength, and unit is 1/ (cm3·s)；
C be the Energy Conversion factor, C=6.24146 × 1012MeV/J；
Power densities of the Pv for nuclear fuel assembly, unit is W/cm；
N is the corresponding fission neutron number of release unit fission energy, N=v/E；
V is the average neutron number that fission is produced every time；And
E is the average energy of fission release every time, and unit is MeV.
In above-mentioned expression formula, parameter Pv, v and E can be from being carried by reactor core monitoring system
For reactor core real time execution supplemental characteristic in obtain or derive.
As the component burn-up level of reactor correspondence particular cycle is different, reactor can be caused not
Have greatly changed with the material section of position.With the intensification of burnup,239Pu、240Pu、241Pu and242The nucleic such as Pu can increase in the accumulation of reactor core diverse location.It is same due to Pu
Isotope unit energy of the position element compared with U produces more neutrons, while the isotope of Pu is produced
Fission neutron is harder than the fission spectrum that produces of isotope of U, penetration capacity is higher.
Therefore, need using consideration v and E altogether when the calculating of pressure vessel Fast neutron flux is carried out
The average mixing fission spectrum of the neutron source strength of same-action and peripheral fuel assembly.
Specifically, the shadow of burnup and newly-generated fission nuclide to source strength is considered in the calculating of source strength
Ring.For during real reaction stack operation, fissioning nucleus have various, therefore final N will consider phase
Answer the fission fraction of different fission nuclides under burn-up level.In one example, v and E takes
Value can be the meansigma methodss of different fission nuclides.Additionally, in the fission adopted when calculating
Sub- power spectrum, as the fission spectrum of different fissilenuclides is different, and with burnup
Deepen, the fission fraction of the different fission nuclides of reactor core is continually changing, and different fission nuclides
The neutron population of fission releasing, disintegration energy are all not quite similar every time, therefore in one example, can
So that the nucleic under the average v values and different burn-up levels based on each combustible component to be split
Become the mixing fission spectrum of share acquisition as in fission when calculating Fast neutron flux
Sub- power spectrum, improves the accuracy and real-time of power spectrum.
Fig. 2 shows the Fast neutron flux of the pressure vessel for real-time monitoring reactor
One example of system.As described above, the system mainly includes from reactor core monitoring system receiving
The data receipt unit 3 of the real time execution supplemental characteristic of reactor core, according to receive supplemental characteristic
The result of the Fast neutron flux that the computing unit 5 and output for calculating neutron fluence rate is calculated
Display unit 6.
Optionally, for real-time monitoring reactor pressure vessel Fast neutron flux should
System can also be including one or more in following units or part：
Prepare computing unit 1, which is responsible for file, the preparation of data, opening, initialization of variable
Deng work, every routine interface is checked, mainly the basic parameter of reactor is initialized,
Generate data base and calculate content needed for monitoring, it is ensured that the complete correctness of each side before calculating；
Time stepping control unit 2, which is configured to the prison that real-time monitoring system is set and controlled
Measured frequency, i.e. which determines the real time execution parameter and monitoring reactor pressure of system acquisition reactor core
The frequency of the Fast neutron flux of container, but monitoring journey can be started at once when certain situation occurs
Sequence；
Finish message unit 4, which is configured to basic parameter (the input ginseng for arranging processing reactor core
Number) and the real time execution supplemental characteristic that receives, formed and meet neutron fluence rate computing unit institute
The form of needs；
Analysis and alarm unit (not shown), which may be configured to carry out point for result of calculation
Analysis, such as runs into abnormal condition and is reported to the police；For example, analysis and alarm unit can be according to meters
The Fast neutron flux for calculating performs one or more in operations described below：Analysis nominal situation；
The exceeded warning of fluence rate；With fluence rate Cause Analysis on Excess etc.；
Report an error unit (not shown), and which is configured to export error information when system operation malfunctions,
Or user input exports warning message when unreasonable；
File management unit 7, which is configured to the process text for recording, managing in calculating process
Shelves, and carry out sorting out, store, it is easy to follow-up access.Subsequently, new monitoring can be carried out
Operation.
It is appreciated that these units listed above or part and the operation that especially performs are simultaneously
Not all be it is necessary, can be according to the fast neutron fluence of the pressure vessel of real-time monitoring reactor
The demand of rate is added in system or method and step.And, these units or part can be
It is by independent device or Implement of Function Module, it is also possible to be integrated in a unit, such as central
Processor.
Result of calculation is divided in real time by embodiments in accordance with the present invention using reactor core monitoring system
Analysis is processed and output, is relied on and is fed back in reactor core monitoring system, and traditional pressure vessel is shielded
Design is combined with irradiation with reactor core real-time monitoring so that is calculated and is supervised simpler and just
It is prompt；Reactor core real-time parameter data receipt unit is provided with, such that it is able to read reactor core source in real time
Item data, calculates pressure vessel Fast neutron flux more accurate.By the enforcement of the present invention
The method and system that example is provided, can effectively improve the efficiency and essence of pressure vessel irradiation
Degree, to npp safety and lengthens the life with obvious gain effect.
It is appreciated that the pressure for real-time monitoring reactor provided in embodiments of the invention
In the method and system of the Fast neutron flux of force container, heap-type is not limited, be suitable for
Monitor in the pressure vessel Fast neutron flux of any heap-type.
Although an embodiment of the present invention has been shown and described, for the ordinary skill of this area
For personnel, it is possible to understand that without departing from the principles and spirit of the present invention can be to this
A little embodiments are changed, and the scope of the present invention be defined by the appended.
Claims (17)
1. a kind of real-time monitoring system of the Fast neutron flux of the pressure vessel of reactor, the reaction
Heap includes the reactor core monitoring system of the operational factor for the reactor core in monitoring pressure in real time container, should
Real-time monitoring system includes：
Data receipt unit, is configured to receive reactor core from reactor core monitoring system with specified monitoring frequency
Real time execution supplemental characteristic；
Neutron fluence rate computing unit, is configured at least based on the real time execution supplemental characteristic for receiving
Calculate the Fast neutron flux of pressure vessel；With
Display unit, is configured to for the Fast neutron flux for calculating to carry out visualization output.
2. real-time monitoring system according to claim 1, wherein the real time execution parameter number
According to realtime power distribution and the real-time combustion of real-time nucleic composition information and nuclear fuel assembly including reactor core
Consumption information.
3. real-time monitoring system according to claim 2, wherein neutron fluence rate computing unit
Including module is transported, this transports module and is configured to based on neutron-transport equation from by the real time execution
The fission neutron source strength and fission spectrum of the reactor core that supplemental characteristic is obtained calculates Fast neutron flux.
4. real-time monitoring system according to claim 3, wherein neutron fluence rate computing unit
It is configured to obtain fission neutron source strength based on expressions below：
Nf=CPvN
Wherein：
Nf is fission neutron source normalization factor, and unit is 1/ (cm3·s)；
C be the Energy Conversion factor, C=6.24146 × 1012MeV/J；
Power densities of the Pv for nuclear fuel assembly, unit is W/cm；
N is the corresponding fission neutron number of release unit fission energy, N=ν/E；
ν is the average neutron number that fission is produced every time；And
E is the average energy of fission release every time, and unit is MeV.
5. real-time monitoring system according to claim 4, wherein fission spectrum is to be based on
It is mixed that nucleic fission fraction under the average ν values of each combustible component and different burn-up levels is obtained
Close fission spectrum.
6. real-time monitoring system according to claim 3, wherein transport module be configured to
DISORT method calculates Fast neutron flux.
7. the real-time monitoring system according to any one of claim 1-6, also including being configured
Into receive reactor basic parameter input block, wherein neutron fluence rate computing unit further by
It is configured to calculate Fast neutron flux based on the basic parameter and real time execution supplemental characteristic that receive.
8. the real-time monitoring system according to any one of claim 1-6, also including being configured
Into the time stepping control unit of the monitoring frequency that real-time monitoring system is set and controlled.
9. the real-time monitoring system according to any one of claim 1-6, also including analysis and
Under alarm unit, the analysis and alarm unit are configured to be performed according to the Fast neutron flux for calculating
State one or more in operation：Analysis nominal situation；The exceeded warning of fluence rate；It is exceeded with fluence rate
The analysis of causes.
10. a kind of method of the Fast neutron flux of the pressure vessel for real-time monitoring reactor,
The reactor includes the reactor core monitoring system of the operational factor for the reactor core in monitoring pressure in real time container
System, the method comprise the steps：
The real time execution supplemental characteristic of reactor core is received with specified monitoring frequency from reactor core monitoring system；
The Fast neutron flux of pressure vessel is calculated based on the real time execution supplemental characteristic for receiving at least；
And
The Fast neutron flux for calculating is carried out into visualization output.
11. methods according to claim 10, wherein the real time execution supplemental characteristic includes
The realtime power distribution of reactor core and the real-time burnup information of real-time nucleic composition information and nuclear fuel assembly.
12. methods according to claim 11, wherein calculating the fast neutron fluence of pressure vessel
The step of rate, is included based on neutron-transport equation from the reactor core obtained by the real time execution supplemental characteristic
Fission neutron source strength and fission spectrum calculate Fast neutron flux.
13. methods according to claim 12, wherein in being fissioned based on expressions below
Component is strong：
Nf=CPvN
Wherein：
Nf is fission neutron source normalization factor, and unit is 1/ (cm3·s)；
C be the Energy Conversion factor, C=6.24146 × 1012MeV/J；
Power densities of the Pv for nuclear fuel assembly, unit is W/cm；
N is the corresponding fission neutron number of release unit fission energy, N=ν/E；
ν is the average neutron number that fission is produced every time；And
E is the average energy of fission release every time, and unit is MeV.
14. methods according to claim 13, wherein by based on the flat of each combustible component
The mixing fission spectrum conduct that nucleic fission fraction under ν values and different burn-up levels is obtained
Fission spectrum.
15. methods according to claim 12, wherein calculating the fast neutron fluence of pressure vessel
The step of rate, includes calculating Fast neutron flux with DISORT method.
16. methods according to any one of claim 10-15, also including reception reactor
The step of basic parameter, and include based on reception the step of calculate the Fast neutron flux of pressure vessel
The basic parameter for arriving and real time execution supplemental characteristic calculate Fast neutron flux.
17. methods according to any one of claim 10-15, also include that basis calculates
Fast neutron flux performs one or more in operations described below：Nominal situation is analyzed；Neutron fluence rate
Exceeded warning；With neutron fluence rate Cause Analysis on Excess.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113205896A (en) * | 2021-03-26 | 2021-08-03 | 中广核研究院有限公司 | Nuclear reactor core monitoring method, device, computer equipment and storage medium |
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