CN107068211A - A kind of method that use postdose fuel element substitutes a neutron source - Google Patents
A kind of method that use postdose fuel element substitutes a neutron source Download PDFInfo
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- CN107068211A CN107068211A CN201710111599.XA CN201710111599A CN107068211A CN 107068211 A CN107068211 A CN 107068211A CN 201710111599 A CN201710111599 A CN 201710111599A CN 107068211 A CN107068211 A CN 107068211A
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- postdose
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- neutron source
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
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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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- 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 use postdose fuel element substitutes a neutron source, reactor core is not loaded and without using a Neutron source assembly, loaded in first circulation it is one or more from it is other run reactor in the postdose fuel assembly that obtains, the neutron discharged using postdose fuel assembly makes the neutron count rate at detector meet requirement, while the fissile nuclide that postdose fuel assembly is retained meets first circulation physics design requirement.The beneficial effects of the invention are as follows：Fuel assembly is after 2 times circulate, generating can be by self-fission reaction and (α, n) reaction produces the nucleic of neutron, simultaneously a large amount of fissile nuclides are still had in fuel, a neutron source is substituted in the case where meeting core loading and starting criticality safety supervision requirement using postdose fuel assembly, it is to avoid the production of the sources of Cf 252, device fabrication and Radiation Protection that a Neutron source assembly is brought.
Description
Technical field
The present invention relates to nuclear reactor designs technical field, in particular it relates to which a kind of substituted using postdose fuel element
The method of neutron source.
Background technology
Reactor is during charging and startup, it is necessary to be monitored to reactor core fission reaction rate and its change, so as to prevent
Reactor reaches uncontrollable prompt criticality state.Domestic in-service nuclear power plant, in head circulations, monitoring uses heap external source
Range detector, introduces a neutron source (generally Cf-252 sources) in reactor core, can improve at detector apart from reactor core farther out
Neutron fluence rate and counting rate.At present, a typical PWR nuclear power plant reactor core, can symmetrically introduce 2 one in reactor core
Secondary Neutron source assembly.
The use of neutron source has the disadvantage that：1) production of Cf-252 sources is difficult, and production cost is high；2) need to design system
A special Neutron source assembly is made, increases extra equipment.
The content of the invention
The technical problems to be solved by the invention are to provide a kind of first use for circulating Neutron source assembly of cancellation spoke
The method that a neutron source is substituted according to fuel element.
The present invention the used technical scheme that solves the above problems is：
A kind of method that use postdose fuel element substitutes a neutron source, reactor core is not loaded and without using a neutron
Source component, loaded in first circulation it is one or more from it is other run reactor in the postdose fuel assembly that obtains, utilize
The neutron of postdose fuel assembly release makes the neutron count rate at detector meet requirement, while postdose fuel assembly is retained
Fissile nuclide meet first circulation physics design requirement.
Further, described reactor core is using 177 fuel assemblies.
Further, described postdose fuel is the fuel assembly by circulating twice.
Further, postdose fuel assembly is arranged in reactor core periphery so that during reactor start-up, at detector
Counting rate and fission neutron portion disclosure satisfy that physical start-up requirement.
Further, early stage head circulation loading stages, postdose fuel assembly is placed in reactor core outermost, i.e., most connect
The position of nearly source range detector；In the later stage of first circulation loading stage, after peripheral fuel assembly is deployed substantially, by institute
State postdose fuel assembly and move to Stowage Plane position from reactor core periphery.During whole charging, counting rate meets dress at detector
Expect detection requirement.
To sum up, the beneficial effects of the invention are as follows：
1st, the present invention proposes the method that a Neutron source assembly is substituted using postdose fuel assembly, high enrichment fuel
Component by 2 times circulate after, generate can by self-fission reaction with (α, n) reaction produce neutron nucleic, simultaneously fire
A large amount of fissile nuclides are still had in material, the postdose fuel stack of these medium burnups is recycled in the head of other reactors
Part, can both meet physical Design requirement, the measurement request of heap external source range detector can be met again.
2nd, can be in Neutron source assembly of first circulation cancellation, will meeting core loading and starting criticality safety supervision
In the case of asking, it is to avoid the production of Cf-252 sources, device fabrication and Radiation Protection that a Neutron source assembly is brought.
3rd, the neutron and the fissile nuclide of retention discharged using postdose fuel, meets first circulating reactor charging and thing
Reason start during criticality safety requirement and physical Design related request, it is to avoid the difficulty that the production of Cf-252 sources is brought, drop
Low reaction heaping equipment purchase cost.
Brief description of the drawings
Fig. 1 is the 177 reactor core PWR nuclear power plant reactor feed order examples using the present invention；
Fig. 2 is to load example using the 177 reactor core PWR nuclear power plant reactors of the present invention.
Embodiment
The present invention will now be described in further detail with reference to the accompanying drawings and the accompanying drawings, but embodiments of the present invention
Not limited to this.
Embodiment：
By taking the PWR nuclear power plant reactor core using 177 fuel assemblies as an example.
As shown in Figure 1-2, a kind of method that use postdose fuel element substitutes a neutron source, cancellation is arranged in reaction
A Neutron source assembly in heap reactor core, early stage head circulation loading stages, is loaded no less than 4 from other in head circulations
The postdose fuel assembly obtained in reactor is run, the fissile nuclide that postdose fuel assembly is retained need to meet first circulation
Physical Design requirement, the neutron discharged using postdose fuel assembly makes the neutron count rate at detector meet requirement, preferably
, postdose fuel assembly is placed in reactor core outermost, i.e., closest to source range detector (i.e. SCR1 in Fig. 1, SCR2)
Position so that during reactor start-up, counting rate and fission neutron portion disclosure satisfy that physical start-up will at detector
Ask, postdose fuel is used in this implementation for fuel assembly, if only with 4 postdose fuel assemblies, single subassembly
Burn-up level should be greater than 40000MWd/tU, if postdose fuel assembly is more, postdose fuel-assembly burn-up is formed
Neutron source strength sum must not be less than the neutron source strength sum that 4 burn-up levels are 40000MWd/tU.
In the later stage of loading stage, after peripheral assembly is deployed substantially, postdose fuel assembly is moved from reactor core periphery
To Stowage Plane position.Using charging order of the present invention as shown in figure 1, selection is in A07, A09 and R07, R09 when charging starts
Postdose fuel assembly is arranged, A08, N06 location arrangements novel fuel assembly said herein is in the charging incipient stage, i.e., before dress
During 6 fuel assemblies, A08, N06 position will arrange New Parent, after fuel assembly close to after installing, when core loading is started
The postdose fuel assembly that A07, A09 and R07, R09 are loaded moves to Stowage Plane position, loads core loading report in the position
Accuse the fuel assembly of defined.But the reactor core of the present invention is not limited to this kind of core loading order.
Described reactor core is using a suitable core loading, and (such as 4 burnups exceed high burnup postdose fuel assembly
40000MWd/tU fuel assembly) it is arranged in reactor core periphery, reactor core and does not arrange that other additional neutron sources (use one as
Secondary neutron source Cf-252), using core loading of the present invention as shown in Fig. 2 B and P row by center (such as B07, B08,
B09 and P07, P08, P09) some postdose fuel assemblies can be arranged, in such a situa-tion, and using limited quantity, limited combustion
The fuel assembly of consumption can just realize that out-pile pulse detector is counted and reach certain level, while ensuring that phase reactor core connects upon actuation
During near critical, the fission neutron share in explorer count is in higher level.But the reactor core of the present invention is not limited to
This kind of core loading.Wherein, in accompanying drawing 2,18000：Enrichment is 1.8%；24000：Enrichment is 2.4%, and boracic is not flammable
Poison rod；24012：Enrichment is 2.4%, containing 12 boron burnable poison rods；24016：Enrichment is 2.4%, can containing 16 boron
Fire poison rod；24020：Enrichment is 2.4%, containing 20 boron burnable poison rods；31000：Enrichment is 3.1%, and boracic can not
Fire poison rod；31008：Enrichment is 3.1%, containing 8 boron burnable poison rods；31016：Enrichment is 3.1%, can containing 16 boron
Fire poison rod；RFA:Postdose fuel assembly.
Reactor core of the present invention cancels a Neutron source assembly in reactor head circulations, is discharged using postdose fuel
Neutron, the criticality safety supervision during meeting reactor feed and physical start-up requires, using existing in postdose fuel assembly
Fissile nuclide, meet reacter phyics design related request.Cancel a Neutron source assembly, it is to avoid Cf-252 sources produce band
The difficulty come, reduces reactor plant purchase cost.
As described above, the present invention can be realized preferably.
Claims (5)
1. a kind of method that use postdose fuel element substitutes a neutron source, it is characterised in that reactor core is not loaded and do not made
With a Neutron source assembly, postdose fuel assembly is loaded in head circulations, the neutron discharged using postdose fuel assembly is made
Neutron count rate at detector, which is met, to be required, the fissile nuclide that postdose fuel assembly is retained meets first circulation physical Design
It is required that.
2. the method that a kind of use postdose fuel element according to claim 1 substitutes a neutron source, its feature exists
In reactor core is using 177 fuel assemblies.
3. the method that a kind of use postdose fuel element according to claim 1 substitutes a neutron source, its feature exists
In postdose fuel is the fuel assembly by circulating more than twice.
4. the method that a kind of use postdose fuel element according to claim 1 substitutes a neutron source, its feature exists
In, by postdose fuel assembly be arranged in reactor core periphery so that during reactor start-up, at detector counting rate and fission in
Sub- portion disclosure satisfy that physical start-up requirement.
5. the method that a kind of use postdose fuel element according to claim 1 or 4 substitutes a neutron source, its feature
It is, early stage head circulation loading stages, postdose fuel assembly is placed in reactor core outermost, i.e., detected closest to source range
The position of device；In the later stage of first circulation loading stage, after peripheral fuel assembly is deployed substantially, by the postdose fuel
Component moves to Stowage Plane position from reactor core periphery.During whole charging, counting rate meets charging detection requirement at detector.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN201710111599.XA CN107068211A (en) | 2017-02-28 | 2017-02-28 | A kind of method that use postdose fuel element substitutes a neutron source |
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| CN201710111599.XA CN107068211A (en) | 2017-02-28 | 2017-02-28 | A kind of method that use postdose fuel element substitutes a neutron source |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109637689A (en) * | 2018-10-23 | 2019-04-16 | 中广核研究院有限公司 | The production method in small cores pile neutron source |
| 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 |
| CN110580957A (en) * | 2019-09-19 | 2019-12-17 | 中国核动力研究设计院 | reactor charging starting method without external neutron source |
| 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 |
| CN112599268A (en) * | 2020-09-07 | 2021-04-02 | 中核核电运行管理有限公司 | Unloading method for replacing secondary neutron source component with central fuel component |
| 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 |
| 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 |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60210797A (en) * | 1984-04-05 | 1985-10-23 | 株式会社東芝 | Neutron source device for starting nuclear reactor |
| CN102243900A (en) * | 2011-06-28 | 2011-11-16 | 中国原子能科学研究院 | Primary neutron source component for starting nuclear reactor |
| CN103345947A (en) * | 2013-07-10 | 2013-10-09 | 中科华核电技术研究院有限公司 | Method for igniting nuclear reactor by using secondary neutron source |
| CN103400619A (en) * | 2013-07-03 | 2013-11-20 | 中国核电工程有限公司 | Advanced loading method for year fuel cycle of 1/4 of reactor core |
| CN105139901A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | Fuel management method of pressurized water reactor core formed by 177 fuel assemblies |
| CN105139899A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | Core loading method of pressurized water reactor nuclear power plant first cycle |
-
2017
- 2017-02-28 CN CN201710111599.XA patent/CN107068211A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60210797A (en) * | 1984-04-05 | 1985-10-23 | 株式会社東芝 | Neutron source device for starting nuclear reactor |
| CN102243900A (en) * | 2011-06-28 | 2011-11-16 | 中国原子能科学研究院 | Primary neutron source component for starting nuclear reactor |
| CN103400619A (en) * | 2013-07-03 | 2013-11-20 | 中国核电工程有限公司 | Advanced loading method for year fuel cycle of 1/4 of reactor core |
| CN103345947A (en) * | 2013-07-10 | 2013-10-09 | 中科华核电技术研究院有限公司 | Method for igniting nuclear reactor by using secondary neutron source |
| CN105139901A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | Fuel management method of pressurized water reactor core formed by 177 fuel assemblies |
| CN105139899A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | Core loading method of pressurized water reactor nuclear power plant first cycle |
Non-Patent Citations (1)
| Title |
|---|
| 谭兴春: "昌江核电厂无二次中子源装料和启动分析", 《设备管理与维修》 * |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109637689A (en) * | 2018-10-23 | 2019-04-16 | 中广核研究院有限公司 | The production method in small cores pile neutron source |
| 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 |
| CN110580957A (en) * | 2019-09-19 | 2019-12-17 | 中国核动力研究设计院 | reactor charging starting method without external neutron source |
| 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 |
| CN112599268A (en) * | 2020-09-07 | 2021-04-02 | 中核核电运行管理有限公司 | Unloading method for replacing secondary neutron source component with central fuel component |
| CN112599268B (en) * | 2020-09-07 | 2023-01-03 | 中核核电运行管理有限公司 | Unloading method for replacing secondary neutron source component with central fuel component |
| 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 |
| 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: 20170818 |