CN106898387A - A kind of method that reactor cancels secondary neutron source - Google Patents
A kind of method that reactor cancels secondary neutron source Download PDFInfo
- Publication number
- CN106898387A CN106898387A CN201710111596.6A CN201710111596A CN106898387A CN 106898387 A CN106898387 A CN 106898387A CN 201710111596 A CN201710111596 A CN 201710111596A CN 106898387 A CN106898387 A CN 106898387A
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- reactor
- reactor core
- neutron source
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/104—Measuring reactivity
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- 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 that reactor cancels secondary neutron source, reactor core is not loaded and does not use secondary neutron source component, and the neutron discharged using the postdose fuel assembly loaded in reactor core requires the neutron count rate satisfaction at detector.The beneficial effects of the invention are as follows：The neutron discharged using postdose fuel, is met the criticality safety supervision during following cycle reactor feed and physical start-up and required；Secondary neutron source component need not be re-introduced into reactor core, following cycle is the monitoring for being capable of achieving reactor start-up process.
Description
Technical field
The present invention relates to nuclear reactor designs technical field, in particular it relates to a kind of reactor cancels secondary neutron source
Method.
Background technology
PWR nuclear power plant reactor is during charging and startup, it is necessary to be supervised to reactor core fission reaction rate and its change
Survey, so as to prevent reactor from reaching uncontrollable prompt criticality state.Domestic in-service nuclear power plant, reactor start-up monitoring is used
Be heap external source range detector, secondary neutron source is introduced in reactor core apart from reactor core farther out, can improve follow-up after head circulations
Neutron fluence rate and counting rate at loop detection device.At present, a typical nuclear power plant pressurized water reactor core, can be symmetrical in reactor core
2 secondary neutron source components of introducing, when following cycle complete reload open heap when, the reading of source range detector-source range detector
Number is generally more than 10cps, much larger than monitoring Minimum requirements.
The use of secondary neutron source has the disadvantage that：1) the extra generation for increasing power plant's tritium and discharge capacity；2) with increase
The risk of Sb-124 specific activitys in primary Ioops cooling agent；3) secondary neutron source has certain life-span, many within nuclear power plant's full phase in longevity
Secondary replacing, increases unnecessary purchase cost.
The content of the invention
The technical problems to be solved by the invention are to provide a kind of method that reactor cancels secondary neutron source, are circulated in head
In the case of meeting following cycle core loading afterwards and starting criticality safety supervision requirement, it is to avoid secondary neutron source component brings
Equipment purchase and Radiation Protection.
The present invention the used technical scheme that solves the above problems is：
A kind of method that reactor cancels secondary neutron source, reactor core is not loaded and does not use secondary neutron source component, is utilized
The neutron of the postdose fuel assembly release loaded in reactor core makes the neutron count rate at detector meet requirement.
Further, reactor core uses 177 fuel assemblies.
Further, early stage loading stage, deep burnup fuel component is placed in reactor core periphery, i.e., closest to source range
The position of detector；Late period loading stage, after peripheral assembly is deployed substantially, by deep burnup fuel component from reactor core
Periphery moves to Stowage Plane position.During whole charging, counting rate meets charging detection requirement at detector.The present invention is by right
Loading sequence is optimized, and proposes technical requirements to core loading scheme, it is ensured that each step charging is placed in effective
Source range monitoring range, avoids monitoring blind area to greatest extent.
Further, the deeper postdose fuel assembly of reactor core burnup is arranged in reactor core periphery so that open in reactor
During dynamic, counting rate and fission neutron portion disclosure satisfy that physical start-up requirement at detector.
To sum up, the beneficial effects of the invention are as follows：
1st, the present invention proposes the method that reactor cancels secondary neutron source, the neutron discharged using postdose fuel, full
Criticality safety supervision during sufficient following cycle reactor feed and physical start-up is required.Nuclear power plant's fuel assembly is by reactor core
After irradiation, generating can be reacted with (α, n) reaction produces the nucleic of neutron, however, relative to secondary neutron by self-fission
Source, the neutron source source strength of these postdose fuel assemblies is relatively low.The present invention, by theory analysis (to new charge schedule and heap
Core is loaded and carries out analytic demonstration, is detected with the detector during meeting charging and opening heap and required), give a new charging time
Sequence is designed and core loading scheme, by such design, secondary neutron source component need not be re-introduced into reactor core, is subsequently followed
Ring is the monitoring for being capable of achieving reactor start-up process.
2nd, present invention eliminates nuclear power plant's reactor secondary neutron source component, after cancelling secondary neutron source, nuclear power plant is reduced
Sb-124 specific activitys in discharge, the reduction reactor-loop cooling agent agent of tritium, reduce the purchase cost of secondary neutron source, gram
The shortcoming of secondary neutron source component is taken.
Brief description of the drawings
Fig. 1 is using 177 reactor core PWR nuclear power plant reactor feed order example of the invention；
Fig. 2 is to load example using 177 reactor core PWR nuclear power plant reactor of the present invention.
Specific embodiment
With reference to embodiment and accompanying drawing, detailed description further, but embodiments of the present invention are made to the present invention
Not limited to this.
Embodiment：
The present embodiment is as a example by using 177 reactor cores of fuel assembly.
As shown in figure 1, a kind of method that reactor cancels secondary neutron source, traditional arrangement is eliminated in reactor core
Secondary neutron source component, early stage reload core loading stage, by deep burnup fuel component, (previous circulation is unloaded, extremely
2 circulations are experienced less) be respectively placed in reactor core periphery, i.e., closest to the position in source range detector (i.e. SRC1, SRC2 in Fig. 1)
Put, arrangement one is at least should ensure that near single detector；In the later stage of loading stage, deployed substantially in peripheral assembly
Afterwards, deep burnup fuel component moves to Stowage Plane position from reactor core periphery, or removes and put back to Spent Fuel Pool.Loading stage is in early days
Refer to that small part fuel has been charged into reactor core, loading stage late period refers to that most of fuel has been charged into reactor core.
It is as shown in Figure 1 using a kind of typical charging order of the present invention.Selection is in A07, A08, A09 when charging starts
And R07, R08, R09 arrange the deeper fuel assembly of burnup of some burn-up levels more than 30000MWd/tU (be such as arranged in A08,
N06 positions), after fuel assembly close to after installing, the A row fuel stack deeper with the burnup that R equips load when core loading is started
Part moves to Stowage Plane position, and the fuel assembly of core loading figure defined is loaded in the position.Stowage Plane, refers to fuel management
The subsequent cycle reactor fuel component layout drawing specified；But reactor core of the invention is not limited to this kind of core loading order.It is deep
Burnup fuel component is specifically referred to：It has been defined as what previous circulation was unloaded, has at least experienced 2 fuel assemblies of circulation.A07、
A08, A09 and R07, R08, R09 should can serve as the position of deep burnup component, and Fig. 1 is a kind of typical situation.
Described reactor core is suitable core loading, and the deeper postdose fuel assembly of reactor core burnup is arranged in outside reactor core
Enclose, using core loading of the present invention as shown in Fig. 2 A row and R column positions, can arrange that some burn-up levels exceed
The fuel assembly of 20000MWd/tU or so, C row and N row by center (such as C06, C07, C08, C09, C10 and N06, N07,
N08, N09, N10) fuel assembly of some burn-up levels more than 30000MWd/tU or so can be arranged.But reactor core of the invention is simultaneously
It is not limited to this kind of core loading.
Before the implementation of above-mentioned charging order, charging order and core loading should be proved by theory analysis, specifically
Method and requirement are：
Postdose fuel-assembly burn-up is analyzed using in-core fuel management program, is analyzed using component burn-up calculation code and fired
Material component fissile nuclide loading amount and neutron source strength (tackling component burnup if necessary to be analyzed by axial segmentation), employ three
Dimension PARTICLE TRANSPORT FROM computing technique walks source range response count for not mixed charging.Result is proved to should ensure that, it is each in loading stage
When step is completed, range DCR in source meets and requires, phase reactor core is close to critical period upon actuation, in explorer count
Fission neutron share is in level higher.
Reactor core of the present invention cancels secondary neutron source in following cycle, the neutron discharged using postdose fuel, full
Criticality safety supervision during sufficient reactor feed and physical start-up is required.After cancelling secondary neutron source, reactor tritium is reduced
Sb-124 specific activitys in discharge, reduction primary Ioops cooling agent, reduce the purchase cost of secondary neutron source.
As described above, the present invention can be realized preferably.
Claims (4)
1. a kind of method that reactor cancels secondary neutron source, it is characterised in that reactor core is not loaded and do not use secondary neutron source
Component, the neutron discharged using the postdose fuel assembly loaded in reactor core makes the neutron count rate at detector meet requirement.
2. the method that a kind of reactor according to claim 1 cancels secondary neutron source, it is characterised in that reactor core is used
177 fuel assemblies.
3. the method that a kind of reactor according to claim 1 cancels secondary neutron source, it is characterised in that in loading stage
Early stage, by deep burnup fuel component be placed in reactor core periphery；Late period loading stage, deployed substantially in peripheral assembly
Afterwards, deep burnup fuel component is moved into Stowage Plane position from reactor core periphery.
4. the method that a kind of reactor according to claim 1 cancels secondary neutron source, it is characterised in that by reactor core burnup
Deeper postdose fuel assembly is arranged in reactor core periphery so that during reactor start-up, counting rate and fission at detector
Neutron portion disclosure satisfy that physical start-up requirement.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201710111596.6A CN106898387A (en) | 2017-02-28 | 2017-02-28 | A kind of method that reactor cancels secondary neutron source |
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| CN201710111596.6A CN106898387A (en) | 2017-02-28 | 2017-02-28 | A kind of method that reactor cancels secondary neutron source |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110322975A (en) * | 2019-06-10 | 2019-10-11 | 中广核研究院有限公司 | A kind of passive starting method of nuclear reactor initial core |
| CN111312419A (en) * | 2020-03-27 | 2020-06-19 | 江苏核电有限公司 | Core loading method for pressurized water reactor primary reactor core without additional primary neutron source |
| CN112599269A (en) * | 2020-09-07 | 2021-04-02 | 中核核电运行管理有限公司 | 650MWe large-scale commercial nuclear power station secondary neutron source-free charging method |
| CN114203317A (en) * | 2021-12-13 | 2022-03-18 | 中国核动力研究设计院 | Method for loading spent fuel assemblies in pressurized water reactor core |
| CN114496315A (en) * | 2022-02-17 | 2022-05-13 | 中国核动力研究设计院 | Method for starting neutron source by taking irradiated fuel assembly as new reactor first cycle |
| CN115171922A (en) * | 2022-07-21 | 2022-10-11 | 中国核动力研究设计院 | Method for loading low-fuel-consumption fuel assemblies in initial reactor core of pressurized water reactor |
| CN115472321A (en) * | 2022-09-20 | 2022-12-13 | 中国核动力研究设计院 | Reactor core loading critical supervision method for first-cycle loading of low-fuel-consumption fuel assemblies |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110322975A (en) * | 2019-06-10 | 2019-10-11 | 中广核研究院有限公司 | A kind of passive starting method of nuclear reactor initial core |
| CN111312419A (en) * | 2020-03-27 | 2020-06-19 | 江苏核电有限公司 | Core loading method for pressurized water reactor primary reactor core without additional primary neutron source |
| CN112599269A (en) * | 2020-09-07 | 2021-04-02 | 中核核电运行管理有限公司 | 650MWe large-scale commercial nuclear power station secondary neutron source-free charging method |
| CN114203317A (en) * | 2021-12-13 | 2022-03-18 | 中国核动力研究设计院 | Method for loading spent fuel assemblies in pressurized water reactor core |
| CN114496315A (en) * | 2022-02-17 | 2022-05-13 | 中国核动力研究设计院 | Method for starting neutron source by taking irradiated fuel assembly as new reactor first cycle |
| CN115171922A (en) * | 2022-07-21 | 2022-10-11 | 中国核动力研究设计院 | Method for loading low-fuel-consumption fuel assemblies in initial reactor core of pressurized water reactor |
| CN115171922B (en) * | 2022-07-21 | 2024-05-07 | 中国核动力研究设计院 | Loading method for loading low-burnup fuel assemblies into pressurized water reactor initial reactor core |
| CN115472321A (en) * | 2022-09-20 | 2022-12-13 | 中国核动力研究设计院 | Reactor core loading critical supervision method for first-cycle loading of low-fuel-consumption fuel assemblies |
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Application publication date: 20170627 |
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