CN107545939A - A kind of core loading method of long period balanced recycle after nuclear power station hoisting power - Google Patents
A kind of core loading method of long period balanced recycle after nuclear power station hoisting power Download PDFInfo
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- CN107545939A CN107545939A CN201710560671.7A CN201710560671A CN107545939A CN 107545939 A CN107545939 A CN 107545939A CN 201710560671 A CN201710560671 A CN 201710560671A CN 107545939 A CN107545939 A CN 107545939A
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- loading method
- fuel assembly
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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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Abstract
The invention belongs to reactor design field, it is related to a kind of core loading method of long period balanced recycle after nuclear power station hoisting power.Described core loading method is that most long fuel assembly of each 72 groups of burning times changed in the group fuel assembly of reactor core 163 be novel fuel assembly, and will run 2 fuel assemblies circulated in refuelling component and be placed in outer angular position., can be after nuclear power station hoisting power more than 4% using the core loading method of the present invention, the reactor reloading pattern for remaining to be balanced circulation by the cycle period before hoisting power loads.
Description
Technical field
The invention belongs to reactor design field, it is related to long period balanced recycle after a kind of nuclear power station hoisting power
Core loading method.
Background technology
Current American-European countries increases total installation of generating capacity by the form of reactor hoisting power.
Domestic nuclear power stations many at present are progressively transitioned into long period from pattern of reloading in year and reloaded pattern, possess power and carry
The condition risen.If implementing power ascension, existing in-core fuel management scheme cannot meet to circulate in reactor long-term plan
The requirement of length is, it is necessary to re-start the design of fuel management scheme.
The content of the invention
The purpose of the present invention is the requirement for nuclear plant safety design, there is provided long period after a kind of nuclear power station hoisting power
The core loading method of balanced recycle, after nuclear power station hoisting power more than 4%, to remain to by the cycle period before hoisting power
The reactor reloading pattern that (about 480 equivalent full power day) is balanced circulation loads.
In order to achieve this, in the embodiment on basis, the present invention provides long period after a kind of nuclear power station hoisting power
The core loading method of balanced recycle, described core loading method are each 72 groups changed in the group fuel assembly of reactor core 163
Burning time most long fuel assembly is novel fuel assembly, and the fuel of 2 circulations will have been run in refuelling component
Component is placed in outer angular position.The length of the cycle of this arrangement reactor core can meet after power per liter still according to current cycle period
Operation.
In a preferred embodiment, long period balanced recycle after a kind of nuclear power station hoisting power of present invention offer
Core loading method, wherein described material-changing method is using not exclusively low leakage loading pattern, (such as 72 groups of novel fuel assemblies have
18 assemblings are loaded in reactor core outermost one and enclosed, and other are loaded in the middle part of reactor core.If completely low leakage loads then all fresh fuel groups
Part is arranged in the middle part of reactor core) carry out the replacing of described fuel assembly.
In a preferred embodiment, long period balanced recycle after a kind of nuclear power station hoisting power of present invention offer
Core loading method, wherein described novel fuel assembly235U enrichments are 4.6%.
In a preferred embodiment, long period balanced recycle after a kind of nuclear power station hoisting power of present invention offer
Core loading method, wherein the novel fuel assembly described in every group includes fuel rod of the 6-30 roots containing gadolinium.
Core loading method provided by the invention, fuel assembly load gadolinium-containing fuel rod, contain gadolinia fuel per group fuel assembly
The quantity of rod has 6,12,18,24 and 30.
In a kind of more preferred embodiment, long period balance is followed after the present invention provides a kind of nuclear power station hoisting power
The core loading method of ring, wherein the Gd containing percentage by weight 5-8% in the fuel rod containing gadolinium2O3。
Beneficial effects of the present invention are as follows：Using the core loading method for distributing bright offer, reactor core can be caused to be lifted
After power 4%, remain to be balanced circulation reactor core operation by the cycle period of 480 equivalent full power days, reactor will not be changed
Long-range operation planning.
Brief description of the drawings
Fig. 1 is the schematic diagram of the core loading method in the specific embodiment of the present invention.
Represented in figure per group fuel assembly with a hexagon.The digitized representation fuel assembly of the row of the top one in hexagon
Number (position)；The period of this fuel assembly of the digitized representation on a middle row left side, this fuel assembly of the digitized representation on the right side
In the position of upper one circulation；The type of this fuel assembly of the digitized representation of a row below.
For example, in the numeral for representing the type of fuel assembly：
46 in " 46-X " represent fuel rod in fuel assembly235U enrichments are 4.6%；
X in " 46-X " behind "-" represents to contain X root gadolinium-containing fuel rods, as 6 expressions contain 6 gadolinium-containing fuel rods.
Embodiment
The embodiment of the present invention is further illustrated below in conjunction with accompanying drawing.
After exemplary nuclear power station hoisting power of the invention in the core loading method of long period balanced recycle, pressure is formed
The fuel assembly of water-water reactor reactor core includes 163 groups altogether.When changing wherein 72 groups of burnings using not exclusively low leakage loading pattern every time
Between most long fuel assembly for novel fuel assembly (wherein2354.6%) U enrichments is, so that reactor core balanced recycle
Length of the cycle reaches length of reloading for 18 months.
Gd in the gadolinium-containing fuel rod of novel fuel assembly2O3The percentage by weight of (for burnable poison) is 5-8%, every group of fuel
6,12,18,24 or 30 gadolinium-containing fuel rods can be contained in component, larger flexibility is brought to design.Specifically, balance is followed
The novel fuel assembly of ring reactor core is divided into five types according to the quantity of gadolinium-containing fuel rod：Contain gadolinia fuel containing 6,12,18,24,30
The novel fuel assembly of rod.
In refuelling component, it is low using part that the fuel assembly for having run 2 circulations is placed in outer angular position
The loading pattern of leakage.
Exemplary core loading method of the invention the post fuel component that reloads distribution as shown in figure 1, fuel assembly
Three fuel recycles are at most undergone in reactor core.
For Core Design limit value and security, the technology for having following several respects considers：
1st, for hoisting power 4%, when calculating using 104% power, while the average value and body of linear power density
Product power density average value all improves 4%.
2nd, the factor that the present invention considers in fuel management design includes enthalpy rise factor, rod power density, moderator temperature
Spend coefficient and discharge burn-up maximum fuel burnup etc..Wherein linear power density is only related to component type to maximum discharge burn-up.Enthalpy liter
The factor and safety analysis relation are larger.In order to continue using current design limit value and leave necessarily conservative allowance, enthalpy rise factor
It is smaller than full-power design point.
3rd, the present invention can meet unit hoisting power by using the balanced recycle loading pattern under more than 104% power
The electricity needs of operation 480 days is remained to after more than 4%.Simultaneously as using a kind of235The fuel of U enrichment types, can subtract
The difficulty of few fuel making, increase the efficiency of fuel making.
Obviously, those skilled in the art can carry out the essence of various changes and modification without departing from the present invention to the present invention
God and scope.So, if belonging to the model of the claims in the present invention and its equivalent technology to these modifications and variations of the present invention
Within enclosing, then the present invention is also intended to comprising including these changes and modification.Above-described embodiment or embodiment are simply to the present invention
For example, the present invention can also be implemented with other ad hoc fashions or other particular forms, without departing from the present invention's
Main idea or substantive characteristics.Therefore, it is regarded as from the point of view of the embodiment of description is in terms of any illustrative and non-limiting.This
The scope of invention should be illustrated that any change equivalent with the intention of claim and scope should also include by appended claims
Within the scope of the invention.
Claims (5)
1. a kind of core loading method of long period balanced recycle after nuclear power station hoisting power, it is characterised in that：Described reactor core
Stowage is that most long fuel assembly of each 72 groups of burning times changed in the group fuel assembly of reactor core 163 is fresh fuel group
Part, and the fuel assembly for having run 2 circulations is placed in outer angular position in refuelling component.
2. core loading method according to claim 1, it is characterised in that：Described material-changing method uses the low leakage in part
Loading pattern carries out the replacing of described fuel assembly.
3. core loading method according to claim 1, it is characterised in that：Described novel fuel assembly235U enrichments
For 4.6%.
4. core loading method according to claim 1, it is characterised in that：Novel fuel assembly described in every group includes 6-
30 fuel rods containing gadolinium.
5. core loading method according to claim 4, it is characterised in that：Contain weight in the described fuel rod containing gadolinium
Percentage 5-8% Gd2O3。
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710560671.7A CN107545939A (en) | 2017-07-11 | 2017-07-11 | A kind of core loading method of long period balanced recycle after nuclear power station hoisting power |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201710560671.7A CN107545939A (en) | 2017-07-11 | 2017-07-11 | A kind of core loading method of long period balanced recycle after nuclear power station hoisting power |
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| CN107545939A true CN107545939A (en) | 2018-01-05 |
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| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
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| RU2353009C2 (en) * | 2007-05-10 | 2009-04-20 | Открытое акционерное общество "Центральное конструкторское бюро машиностроения " (ОАО "ЦКБМ") | Method of pipes extraction and associated device |
| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
| CN103474101A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Nuclear reactor core arrangement of nuclear power station |
| US20160118150A1 (en) * | 2013-01-15 | 2016-04-28 | Westinghouse Electric Company Llc | Method and Apparatus for the Shielded Relocation of a Nuclear Component |
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