CN103000232B - The head of a kind of advanced person circulates stowage of reloading for 18 months - Google Patents
The head of a kind of advanced person circulates stowage of reloading for 18 months Download PDFInfo
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- CN103000232B CN103000232B CN201210517652.3A CN201210517652A CN103000232B CN 103000232 B CN103000232 B CN 103000232B CN 201210517652 A CN201210517652 A CN 201210517652A CN 103000232 B CN103000232 B CN 103000232B
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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 designing technique, be specifically related to the first stowage of reloading for 18 months that circulates of a kind of pressurized-water reactor nuclear power plant reactor core.The reactor core that the method forms for 177 group fuel assemblies, in head circulation, part of fuel assembly uses containing gadolinia fuel assembly, Gd
2o
3for burnable poison material, containing Gd in the gadolinium-containing fuel rod of gadolinia fuel assembly
2o
3with UO
2mix disperse in fuel pellet, containing Gd in gadolinia fuel pellet
2o
3percentage by weight be 2%-10%.The present invention is under the prerequisite meeting every safety criterion, achieving Natural Circulation length is 482 equivalent full power days, compared with the solid combustible poisonous substance using borosilicate glass in circulating with traditional head, length of the cycle has grown 147 equivalent full power days, the balanced recycle length of reloading with 18 months is suitable, has quite high economy and operational flexibility.
Description
Technical field
The invention belongs to reactor designing technique, be specifically related to the first stowage of reloading for 18 months that circulates of a kind of pressurized-water reactor nuclear power plant reactor core.
Background technology
In the first circulating fuel arrangement of components of the pressurized-water reactor nuclear power plant reactor core be made up of 177 group fuel assemblies, traditional method for arranging is: be divided into 3rd district to arrange according to the difference of enrichment reactor fuel assembly, the enrichment in this 3rd district is respectively 1.8%, 2.4%, 3.1%, wherein enrichment is that the fuel assembly of 1.8% is not containing solid combustible poisonous substance, enrichment is may contain solid combustible poisonous substance in the fuel assembly of 2.4% and 3.1%, and the solid combustible poisonous substance used in head circulation is borosilicate glass.Under the prerequisite meeting every safety criterion, the circulate Natural Circulation length of reactor core of the head of traditional arrangement is 335 equivalent full power days.
The solid combustible poisonous substance of traditional borosilicate glass has the following disadvantages: comparatively complicated on manufacture technics, the borosilicate glass of ring-type is contained in stainless sleeve pipe; The guide pipe position of fuel assembly is directly inserted in the form of burnable poison rod, and control rod is also the guide pipe position being inserted in fuel assembly, therefore the fuel assembly inserting burnable poison rod just can not insert control rod again, and that is the use of borosilicate glass burnable poison rod is in the dirigibility limiting control rod design to a certain extent; In addition; after first circulation; need removal borosilicate glass burnable poison rod; carry out extra packaging and process; solid combustible poison rod containing 1248 borosilicate glasses in the reactor core head circulation of 177 group fuel assembly compositions; therefore the radioactive waste additionally caused is the solid combustible poison rod of 1248 borosilicate glasses, is unfavorable for environmental protection.
Summary of the invention
The object of the present invention is to provide a kind of first cyclical loadings method of reactor core of 177 group fuel assemblies compositions, be intended to solve in first circulation use the solid combustible poisonous substance of traditional borosilicate glass cause radioactive waste many, be unfavorable for that environmental protection and upper dumb, the length of the cycle of control rod design differ more problem with the balanced recycle length of to reload for 18 months.
Technical scheme of the present invention is as follows: the head of a kind of advanced person circulates stowage of reloading for 18 months, and reactor core is made up of 177 group fuel assemblies, and in head circulation, part of fuel assembly uses containing gadolinia fuel assembly, Gd
2o
3for burnable poison material, containing Gd in the gadolinium-containing fuel rod of gadolinia fuel assembly
2o
3with UO
2mix disperse in fuel pellet, containing Gd in gadolinia fuel pellet
2o
3percentage by weight be 2%-10%.
Further, head as above advanced circulates stowage of reloading for 18 months, wherein, 177 described group fuel assemblies according to
235the enrichment difference of U is divided into 3rd district, three district's enrichments are respectively 2.0%, 3.1% and 3.9%, the fuel stack number of packages in 3rd district is followed successively by 61,68 and 48 groups, wherein enrichment is do not have gadolinium-containing fuel rod in the fuel assembly of 2.0%, and enrichment is containing gadolinium-containing fuel rod in the fuel assembly of 3.1% and 3.9%.
Further, 4,8,12,16,20 or 24 gadolinium-containing fuel rods are being contained containing in gadolinia fuel assembly.
Further, the head of advanced person as above circulates stowage of reloading for 18 months, wherein, in the fuel assembly subregion of three kinds of described enrichments, the fuel assembly that enrichment is the highest is loaded in reactor core outskirt, and other two kinds are arranged in reactor core inner region compared with the fuel assembly of low enrichment by checkerboard type.
Beneficial effect of the present invention is as follows: the present invention adopts Gd in head circulation
2o
3as burnable poison, under the prerequisite meeting every safety criterion, achieving Natural Circulation length is 482 equivalent full power days, compared with the solid combustible poisonous substance using borosilicate glass in circulating with traditional head, length of the cycle has grown 147 equivalent full power days, the balanced recycle length of reloading with 18 months is suitable, has quite high economy and operational flexibility.
Compare the solid combustible poisonous substance of traditional borosilicate glass, adopt Gd
2o
3burnable poison material also have the following advantages: manufacture technics is comparatively simple, Gd
2o
3with UO
2mix disperse in fuel pellet; Do not take guide pipe position, therefore can not interfere with the design attitude of control rod; Do not need to carry out extra process, because Gd
2o
3reduce along with the burnup of heap in-core, there is no remnants, so there is no radioactive waste, be conducive to environmental protection.
Accompanying drawing explanation
Fig. 1 is the arrangement schematic diagram of reactor fuel assembly in specific embodiments of the invention.
In figure,
represent
235u enrichment is the fuel assembly of 3.9%;
represent
235u enrichment is the fuel assembly of 3.1%;
□represent
235u enrichment is the fuel assembly of 2.0%;
The radical of the numeral gadolinium-containing fuel rod in icon.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail.
As shown in Figure 1, in one embodiment of the present of invention, in the reactor core head circulation of 177 group fuel assembly compositions, use Gd
2o
3as burnable poison, improve fuel assembly initial enrichment, rearrange the position of fuel assembly at heap in-core, make the length of the cycle of first circulation reach 18 months to reload length.
The reactor core of 177 group fuel assembly compositions is made up of 177 groups of AFA3G fuel assemblies, and reactor fuel active section height is 365.76cm, and equivalent diameter is 322.8cm, and ratio of height to diameter is 1.13.The fuel rod of each AFA3G fuel assembly, by 17 × 17 square formation arrangements, comprises 264 fuel rods, 24 guide pipes and 1 gauge pipe.
Containing Gd in gadolinia fuel pellet in first circulation
2o
3percentage by weight can from 2% to 10% not etc., as one embodiment of the present of invention, containing Gd in gadolinia fuel pellet in first circulation
2o
3percentage by weight be 8%.
In 17 × 17 fuel assemblies, can 4,8,12,16,20 or 24 gadolinium rods be contained, bring larger dirigibility to design.In the embodiment of the present invention, the fuel assembly of first circulation reactor core is divided into Four types as follows according to the quantity of gadolinium-containing fuel rod: containing the fuel assembly of 8,12,16,20 gadolinium rods.
In first circulation, Gd
2o
3as solid combustible poisonous substance, be structurally and UO
2mix and sinter at UO
2in pellet, therefore use Gd
2o
3do not take the position of guide pipe in fuel assembly as solid combustible poisonous substance, control rod inserts guide pipe position, therefore uses Gd
2o
3as solid combustible poisonous substance, do not interfere with the Position Design of control rod, compare the situation that the solid combustible poisonous substance of traditional use borosilicate glass and control rod Position Design interfere, improve the dirigibility of control rod Position Design to the full extent; In addition, Gd is used
2o
3can also realize controlling preferably beginning of life moderator temperature coefficient.Due to Gd
2o
3be and UO
2pellet sinters together, do not increase the refuse amount outside spentnuclear fuel, and borosilicate glass is as inserting type assembly, needs to carry out extra packaging and process, additionally can cause radioactive waste.Meanwhile, Gd
2o
3manufacturing process comparatively simple easily, and borosilicate glass burnable poison is as inserting type assembly, comparatively complicated in manufacture.
In first circulation, initial core fuel assembly is all novel fuel assembly, according to
235the enrichment difference of U is divided into 3rd district, and three district's enrichments are respectively 2.0%, 3.1% and 3.9%, and fuel stack number of packages is followed successively by 61,68 and 48 groups, and wherein enrichment is may contain gadolinium-containing fuel rod in the fuel assembly of 3.1% and 3.9%.The fuel assembly that enrichment is the highest is loaded in reactor core outskirt, and other two kinds are arranged in reactor core inner region compared with the fuel assembly of low enrichment by checkerboard type.
Fig. 1 is the schematic diagram of reactor fuel arrangement of components in the first cyclical loadings method of reactor core of the 177 group fuel assembly compositions that the embodiment of the present invention provides, the number of gadolinium-containing fuel rod in the numeral assembly wherein in icon.
Horizontal ordinate is turned left from the right side and is arranged by A-R successively, ordinate is arranged by 1-15 from top to bottom successively, in head circulation, the B08 of initial core, C05, C07, C09, C11, D04, D06, D08, D10, D12, E03, E05, E07, E09, E11, E13, F04, F06, F08, F10, F12, G03, G05, G07, G09, G11, G13, H02, H04, H06, H08, H10, H12, H14, J03, J05, J07, J09, J11, J13, K04, K06, K08, K10, K12, L03, L05, L07, L09, L11, L13, M04, M06, M08, M10, M12, N05, N07, N09, N11, P08 location arrangements
235u enrichment is the fuel assembly of 2.0%, and the fuel assembly of this enrichment is not all containing gadolinium-containing fuel rod.
At the B 06 of initial core, B07, B09, B10, C06, C08, C10, D05, D07, D09, D11, E04, E06, E08, E10, E12, F02, F03, F05, F07, F09, F11, F13, F14, G02, G04, G06, G08, G10, G12, G14, H03, H05, H07, H09, H11, H13, J02, J04, J06, J08, J10, J12, J14, K02, K03, K05, K07, K09, K11, K13, K14, L04, L06, L08, L10, L12, M05, M07, M09, M11, N06, N08, N10, P06, P07, P09, P10 location arrangements
235u enrichment is the fuel assembly of 3.1%, wherein contains 8 gadolinium-containing fuel rods at the fuel assembly of B06, B10, F02, F14, K02, K14, P06, P10 location arrangements, 16 gadolinium-containing fuel rods are contained at the fuel assembly of B07, B09, C06, C08, C10, D05, D11, E04, E08, E12, F03, F07, F09, F13, G02, G06, G10, G14, H03, H05, H11, H13, J02, J06, J10, J14, K03, K07, K09, K13, L04, L08, L12, M05, M11, N06, N08, N10, P07, P09 location arrangements, 20 gadolinium-containing fuel rods are contained at the fuel assembly of D07, D09, E06, E10, F05, F11, G04, G08, G12, H07, H09, J04, J08, J12, K05, K11, L06, L10, M07, M09 location arrangements.
In A06, A07, A08, A09, A10, B04, B05, B11, B12, C03, C04, C12, C13, D02, D03, D13, D14, E02, E14, F01, F15, G01, G15, H01, H15, J01, J15, K01, K15, L02, L14, M02, M03, M13, M14, N03, N04, N12, N13, P04, P05, P11, P12, R06, R07, R08, R09, R10 location arrangements of initial core
235u enrichment is the fuel assembly of 3.9%, wherein contains 12 gadolinium-containing fuel rods at the fuel assembly of B05, B11, E02, E14, L02, L14, P05, P11 location arrangements; 16 gadolinium-containing fuel rods are contained at the fuel assembly of A08, H01, H15, R08 location arrangements; 20 gadolinium-containing fuel rods are contained at the fuel assembly of C04, C12, D03, D13, M03, M13, N04, N12 location arrangements.
It is under the prerequisite of basic security criterion that core loading optimal design is arranged, has considered that fuel management performance parameter and neutronics parameter draw.As shown in Table 1, neutronics parameter result of calculation as shown in Table 2 for the fuel management result of calculation of first circulation.
Table one fuel management result of calculation
Table two neutronics parameter result of calculation
| Major parameter | Numerical value |
| Moderator-density coefficient-maximal value (10 5pcm/g/cm 3） | 0.388 |
| Doppler's temperature coefficient (maximum absolute value value) pcm/ DEG C | -4.121 |
| Doppler's temperature coefficient (absolute value minimum value) pcm/ DEG C | -1.894 |
| Doppler power coefficient (low limit value) pcm/%FP | -6.888--5.253(0%-100%) |
| Doppler power coefficient (ceiling value) pcm/%FP | -12.199--9.402(0%1-00%) |
| Delayed neutron fraction-maximal value | 0.00733 |
| Delayed neutron fraction-minimum value | 0.00480 |
| Prompt neutron removal lifetime (maximal value) | 27.657 |
Initial core loading pattern in above head circulation meets basic design parameters: F
dH≤ 1.65; F
q≤ 2.45 and basic security criterion, wherein F
dHfor enthalpy rise factor, F
qfor hot spot factor.Can draw in this scheme head circulation from the result of calculation table one and table two and completely safety criterion is met to the design proposal of novel fuel assembly.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if belong within the scope of the claims in the present invention and equivalent technology thereof to these amendments of the present invention and modification, then the present invention is also intended to comprise these change and modification.
Claims (2)
1. advanced head circulates a stowage of reloading for 18 months, and reactor core is made up of 177 group fuel assemblies, it is characterized in that: the core loading of first circulation, according to
235the enrichment difference of U is divided into 3rd district, and three district's enrichments are respectively 2.0%, 3.1% and 3.9%, and the fuel stack number of packages in 3rd district is followed successively by 61,68 and 48 groups; The fuel assembly that enrichment is the highest is loaded in reactor core outskirt, and other two kinds are arranged in reactor core inner region compared with the fuel assembly of low enrichment by checkerboard type; Part of fuel assembly uses containing gadolinia fuel assembly, Gd
2o
3for burnable poison material, containing Gd in the gadolinium-containing fuel rod of gadolinia fuel assembly
2o
3with UO
2mix disperse in fuel pellet, containing Gd in gadolinia fuel pellet
2o
3percentage by weight be 2%-10%; The head arranged as stated above circulates reactor core, and phase in longevity length reaches 18 months.
2. head as claimed in claim 1 advanced circulates stowage of reloading for 18 months, and it is characterized in that: enrichment is do not have gadolinium-containing fuel rod in the fuel assembly of 2.0%, enrichment is containing gadolinium-containing fuel rod in the fuel assembly of 3.1% and 3.9%.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210517652.3A CN103000232B (en) | 2012-12-05 | 2012-12-05 | The head of a kind of advanced person circulates stowage of reloading for 18 months |
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|---|---|---|---|
| CN201210517652.3A CN103000232B (en) | 2012-12-05 | 2012-12-05 | The head of a kind of advanced person circulates stowage of reloading for 18 months |
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| CN103000232A CN103000232A (en) | 2013-03-27 |
| CN103000232B true CN103000232B (en) | 2015-07-29 |
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Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103578588A (en) * | 2013-10-18 | 2014-02-12 | 中国核电工程有限公司 | Reactor core loading method for exchanging fuels of pressurized water reactor nuclear power plant after 18 months of balanced circulation |
| CN103680652B (en) * | 2013-12-03 | 2016-08-17 | 中国核电工程有限公司 | First circulation uses the core loading method of the fuel assembly of a kind of enrichment |
| CN103985422B (en) * | 2014-03-20 | 2017-03-01 | 中国核动力研究设计院 | Based on the active of 177 reactor cores plus passive nuclear steam supply system and its nuclear power station |
| CN105280256A (en) * | 2014-05-29 | 2016-01-27 | 江苏核电有限公司 | Leading fuel assembly mixing reactor core loading method |
| CN104952492B (en) * | 2015-05-11 | 2017-08-01 | 中国核动力研究设计院 | Carry gadolinia fuel rod and with the fuel assembly and pressurized water reactor core for carrying gadolinia fuel rod |
| CN105139900B (en) * | 2015-07-09 | 2017-04-05 | 中国核动力研究设计院 | A kind of 24 months reload core stowages of employing erbium burnable poison |
| CN107093479A (en) * | 2017-03-30 | 2017-08-25 | 中国核电工程有限公司 | A kind of first circulatory life-time length core loading method of 24 months of presurized water reactor |
| CN107863166B (en) * | 2017-12-08 | 2019-12-24 | 中国核动力研究设计院 | 18-month refueling loading method for pressurized water reactor first-cycle boron-containing reactor core |
| CN107910078B (en) * | 2017-12-08 | 2020-01-10 | 中国核动力研究设计院 | Management method for 18-month refueling multi-cycle fuel of pressurized water reactor core |
| CN108053904B (en) * | 2017-12-08 | 2019-09-24 | 中国核动力研究设计院 | A kind of 18 months stowages of reloading of presurized water reactor head circulation reactor core containing gadolinium |
| CN108039216B (en) * | 2017-12-08 | 2019-09-24 | 中国核动力研究设计院 | A kind of balanced recycle 18 months stowages of reloading of pressurized water reactor core |
| CN113496784B (en) * | 2020-04-03 | 2024-04-19 | 华龙国际核电技术有限公司 | Nuclear power station reactor core |
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