CN102332315B - Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant - Google Patents
Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant Download PDFInfo
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Abstract
The invention is applicable to the field of fuel management on reactor cores of pressurized water reactors, and provides a refueling method for fuel assemblies of a reactor core of a PWR (pressurized water reactor) nuclear power plant. The method comprises: classifying the fuel assemblies of the reactor core into three enrichment areas according to different enrichment degrees; in an initial cycle, respectively adding 8, 12 and 16 burnable poison rods into the fuel assemblies, and according to a cycle length of 18 months, placing the fuel assemblies with high enrichment degree outside the reactor core, and placing the fuel assemblies with low enrichment degree in the reactor core, wherein the enrichment degrees of the fuel assemblies of an initial reactor core are respectively 3.9%, 3.1% and 2.0%; and in subsequent cycles, starting from a second cycle, and rapidly transitioning the subsequent cycles to an equilibrium cycle according to an enrichment degree of 4.45%, wherein a mode of 18-month refueling is adopted, and the fuel assemblies of 1/2-1/3 of the reactor core are replaced every time; meanwhile, placing the new fuel assemblies in the reactor core, and placing the fuel assemblies which are burned outside the reactor core. By using the refueling method provided by the invention, the cycle period is extended, the fuel consumption is improved, and the purpose of completely low neutron leak loading is achieved in the subsequent cycles.
Description
Dividing an application of the application for a patent for invention that the application's application number that to be applicant submit on September 26th, 2007 is 200710077351.2, is attached to the application by its full content by reference.
Technical field
The invention belongs to pressurized water reactor core fuel management field, relate in particular to 18 months material-changing methods of reactor core fuel assembly in Chinese pressurized-water reactor nuclear power plant gigawatt unit.
Background technology
In pressurized-water reactor nuclear power plant reactor core fuel assembly is arranged, the loading pattern of traditional reactor in-core is high-leakage (OUT-IN) pattern, be about to reactor fuel assembly and be divided into 3 enrichment regions according to the difference of enrichment, the fuel assembly that wherein enrichment is the highest is placed on the outskirt of reactor core, and the lower fuel assembly of other two kinds of enrichments is arranged in reactor core inner region in the mode of chessboard.When reloading, normally year reloads, reload at every turn and change 1/3 reactor fuel assembly, the fuel assembly that burnup is the darkest is taken away, novel fuel assembly is put into outskirt, all the other burnup fuel assembly at reactor core inner region, rearrange, rearrange according to be make as far as possible reactor core radially power be evenly distributed.
This traditional core loading pattern, the initial core fuel assembly enrichment in first circulation is lower, and the length of the cycle of realization is shorter, be about 330 equivalent full power days (Effective Full Power Days, EFPD), burnup is low, and fuel utilization economy is not fine.And adopting the loading pattern of OUT-IN while reloading in follow-up circulation, the shortcoming of this loading pattern is to cause neutron leakage rate high because novel fuel assembly is arranged in reactor core outskirt, thereby the pressure vessel life-span is reduced to such an extent as to has affected life-span of whole nuclear power station.
Summary of the invention
The object of the embodiment of the present invention is to provide 18 months material-changing methods of reactor core fuel assembly in a kind of pressurized-water reactor nuclear power plant gigawatt unit, be intended to solve traditional reactor fuel assembly and adopt each method of upgrading 1/3 fuel assembly of reloading in OUT-IN mode arrangement and year, cause the problem that fuel assembly cycle period is short, burnup is low.
The embodiment of the present invention is achieved in that a kind of pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method, comprises the steps:
Reactor core fuel assembly is divided into three enrichment regions according to the difference of enrichment;
In first circulation, 8,12,16 burnable poison rods of fuel assembly band that add burnable poison, length of the cycle by 18 months, the fuel assembly of high enrichment is placed in to reactor core outskirt, the fuel assembly of low enrichment is placed in to reactor core inner region, and just the enrichment of reactor fuel assembly is respectively 3.9%, 3.1% and 2.0%;
In follow-up circulation, since the second circulation, utilization removes to replace with the novel fuel assembly of burnable poison rod the fuel assembly that burnup is crossed, enrichment by 4.45%, adopt and reload for 18 months, each fuel assembly of changing 1/3～1/2 reactor core, and novel fuel assembly is placed in to reactor core inner region, the fuel assembly that burnup has been crossed is placed in reactor core outskirt.
The embodiment of the present invention adopts above-mentioned pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method, improved the enrichment of initial core fuel assembly, change the arrangement of burnable poison, make first circulation realize the length of the cycle of 473 equivalent full power days, extended cycle period; Realize lower power peak factor, met world security criterion; Improve burnup, in follow-up circulation, realized completely low neutron leakage and loaded, had quite high economy and operational flexibility.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of first circulation reactor fuel arrangement of components in 18 months material-changing methods of Chinese pressurized-water reactor nuclear power plant gigawatt unit of providing of the embodiment of the present invention, and it expresses the layout of 1/4th reactor cores;
Fig. 2 is the schematic diagram of balanced recycle reactor fuel arrangement of components in 18 months material-changing methods of Chinese pressurized-water reactor nuclear power plant gigawatt unit of providing of the embodiment of the present invention, and it expresses the layout of 1/4th reactor cores.
Embodiment
In order to make object of the present invention, technical scheme and advantage clearer, below in conjunction with drawings and Examples, the present invention is further elaborated.Should be appreciated that specific embodiment described herein, only in order to explain the present invention, is not intended to limit the present invention.
The embodiment of the present invention, in first circulation, is placed in reactor core outskirt by the fuel assembly of high enrichment, and the fuel assembly of low enrichment is placed in to reactor core inner region; In follow-up circulation, novel fuel assembly is placed in to reactor core inner region, the fuel assembly that burnup has been crossed is placed in reactor core outskirt.By improving the enrichment of fuel assembly, change the number of burnable poison, realized completely low leakage and loaded.
Pressurized-water reactor nuclear power plant reactor core consists of the AFA3G fuel assembly of 157 groups of full M5 materials, and reactor fuel active section height is 365.76cm, equivalent diameter 304.04cm, and ratio of height to diameter is 1.203.Each full M5AFA3G fuel assembly fuel rod is arranged by 17 * 17 square formations, removes 24 guide pipes and 1 gauge pipe, totally 264 fuel rods.
In embodiments of the present invention, the first circulation (first circulation) reactor fuel assembly is all New Parent, by the enrichment difference of 235U, is divided into three enrichment regions.The enrichment of three enrichment regions can be respectively 2.0%, 3.1% and 3.9%, and fuel stack number of packages is respectively 45,56 and 56, as shown in Table 1.The fuel assembly that enrichment is the highest is contained in reactor core outskirt, and the lower fuel assembly of other two kinds of enrichments is arranged in reactor core inner region by checkerboard type, and the shallow assembly of burnup is surrounded to flatten core power by the dark assembly of burnup and distributes.
Table one
Fig. 1 is the schematic diagram of first circulation reactor fuel arrangement of components in 18 months material-changing methods of Chinese pressurized-water reactor nuclear power plant gigawatt unit of providing of the embodiment of the present invention, because the fuel assembly layout of full reactor core is followed 1/4 Rotational Symmetry, in figure, only provided the layout of 1/4th reactor cores; Wherein n represents the number of burnable poison rod.
Horizontal ordinate is arranged by A-H to inner lane successively from outer ring, ordinate is arranged by 08-15 to outer ring successively from inner lane, in the position of H15, the G15 of reactor core, G14, F14, E14, H13, E13, D13, C12, C11, B11, B10, B09, A09, C08, A08, puts
235u enrichment is 3.9% fuel assembly, wherein in the position of coordinate G14, H13, E13, C11, B09, C08, puts fuel assembly and contains the fuel assembly with 16 burnable poison rods.
Put position at F13, the G12 of reactor core, E12, D12, H11, F11, E11, D11, G10, E10, C10, H09, F09, D09, G08, E08
235u enrichment is 3.1% fuel assembly, and the fuel assembly of wherein putting in the position of F13, G12, E12, D12, E11, D11, C10, D09 contains the fuel assembly with 12 burnable poison rods; The fuel assembly of putting in the position of H11, F11, G10, E10, H09, F09, G08, E08 contains the fuel assembly with 8 burnable poison rods.
Put position at H14, the G13 of reactor core, H12, F12, G11, H10, F10, D10, G09, E09, C09, H08, F08, D08, B08
235u enrichment is 2.0% fuel assembly, the fuel assembly of wherein putting in the position of H08 contains the fuel assembly with 12 burnable poison rods, and the fuel assembly of putting in the position of H14, G13, H12, F12, G11, H10, F10, D10, G09, E09, C09, F08, D08, B08 contains the fuel assembly with 8 burnable poison rods.
In follow-up circulation, when reactor fuel assembly need to reload, utilize the novel fuel assembly with burnable poison rod to remove to replace the fuel assembly that burnup is crossed, and further improve
235u enrichment.In the embodiment of the present invention, can in second and third circulation, utilize
235u enrichment is that 60 groups of novel fuel assemblies of 4.45% remove to replace burnup fuel assembly, and corresponding length of the cycle has reached 425EFPD.From the 4th, be recycled to the 6th circulation, all utilizations
235u enrichment is that 68 groups of novel fuel assemblies of 4.45% remove to replace burnup fuel assembly.
Concrete reactor fuel arrangement of components mode is on the basis of head circulation, by what the core loading search of follow-up circulation was drawn.Core loading search is under the prerequisite of basic security criterion, has considered that fuel management performance parameter and neutronics parameter draw.As shown in Table 2, neutronics calculation of parameter result as shown in Table 3 for concrete fuel management result of calculation.
Table two
Table three
In embodiments of the present invention, balanced recycle is used
235u enrichment is that 68 groups of full M5AFA3G fuel assemblies of 4.45% remove to replace burnup assembly.In balanced recycle, reactor fuel arrangement of components adopts completely low leakage IN-OUT load mode, be that novel fuel assembly is placed in reactor core inner region, the part assembly of burnup is placed on reactor core outskirt, thereby reduces the leakage of neutron, the utilization factor of raising neutron, reaches the object that increases circulatory life-time.
Fig. 2 is the schematic diagram of balanced recycle reactor fuel arrangement of components in 18 months material-changing methods of Chinese pressurized-water reactor nuclear power plant gigawatt unit of providing of the embodiment of the present invention, and it expresses the layout of 1/4th reactor cores.
Horizontal ordinate is arranged by A-H to inner lane successively from outer ring, ordinate is arranged by 08-15 to outer ring successively from inner lane, novel fuel assembly is changed in H14, G14, G13, F13, E13, E12, D12, G11, D11, C11, H10, F10, C10, G09, E09, C09, B09, F08, B08 position at reactor core, other position is piled and is put the old fuel assembly that burnup is crossed, the position of the old fuel assembly that combines to represent burnup with letter and number in figure in a upper circulation.As H10 represents that the position of this old fuel assembly in a upper circulation is H10.
In embodiments of the present invention, from balanced recycle reactor reloading pattern is arranged, all adopt low neutron leakage IN-OUT load mode, the assembly enrichment that reloads of every batch is 4.45%, and balanced recycle reactor reloading pattern component count is 68 groups, and length of the cycle can reach 480EFPD.
Just core loading scheme meets basic design parameters above: FDH≤1.55; FQ≤2.45 and basic security criterion, the power peak factor obtaining is quite low, and for thermal technology's safety analysis provides enough allowances, wherein FDH is enthalpy rise factor, and FQ is hot spot factor.In the core loading scheme of follow-up circulation, according to international standard, improved design parameter: FDH≤1.65; FQ≤2.45 bring up to 4.45% by the enrichment of the assembly that reloads simultaneously, and the accident of secondary circuit are carried out to the evaluate and analyze of system, determine that the change of fuel management is very little on the crash analysis impact of secondary circuit.Result of calculation from table two and table three can show that this design proposal meets world security criterion completely.
18 months material-changing methods of embodiment of the present invention China's pressurized-water reactor nuclear power plant gigawatt unit, in first circulation, improve the enrichment of initial core fuel assembly, change the arrangement of burnable poison, make Natural Circulation length reach 473EFPD, with the first circulation of pressurized-water reactor nuclear power plant in prior art be all reload in year (about 330EFPD) compare, extended cycle period, improved burnup; In follow-up circulation, further improve the enrichment of fuel assembly, fast transition is to balanced recycle, adopt and reload for 18 months, each fuel assembly of changing 1/2～1/3 reactor core, and novel fuel assembly is placed in to reactor core inner region, the fuel assembly that burnup has been crossed is placed in reactor core outskirt, realize completely low neutron leakage and loaded, had quite high economy and operational flexibility.
The foregoing is only preferred embodiment of the present invention, not in order to limit the present invention, all any modifications of doing within the spirit and principles in the present invention, be equal to and replace and improvement etc., within all should being included in protection scope of the present invention.
Claims (8)
1. a pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method, is characterized in that, comprises the steps:
Reactor core fuel assembly is divided into three enrichment regions according to the difference of enrichment;
In first circulation, 8,12,16 burnable poison rods of fuel assembly band that add burnable poison, length of the cycle by 18 months, the fuel assembly of high enrichment is placed in to reactor core outskirt, the fuel assembly of low enrichment is placed in to reactor core inner region, and just the enrichment of reactor fuel assembly is respectively 3.9%, 3.1% and 2.0%;
In follow-up circulation, since the second circulation, utilization removes to replace with the novel fuel assembly of burnable poison rod the fuel assembly that burnup is crossed, enrichment by 4.45%, adopt and reload for 18 months, each fuel assembly of changing 1/3～1/2 reactor core, and novel fuel assembly is placed in to reactor core inner region, the fuel assembly that burnup has been crossed is placed in reactor core outskirt.
2. pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method as claimed in claim 1, is characterized in that, the described just load mode of reactor core meets basic design parameters: FDH≤1.55; FQ≤2.45, the core loading mode of follow-up circulation meets design parameter: FDH≤1.65; FQ≤2.45, wherein FDH is enthalpy rise factor, FQ is hot spot factor.
3. pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method as claimed in claim 1, is characterized in that, described follow-up circulation is transition cycles and balanced recycle.
4. the pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method as described in claim 1-3 any one, it is characterized in that, described reactor core consists of the AFA3G fuel assembly of 157 groups of full M5 materials, the active section height of its reactor fuel is 365.76cm, equivalent diameter 304.04cm, ratio of height to diameter is 1.203.
5. pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method as claimed in claim 4, is characterized in that, the fuel rod of each fuel assembly is arranged by 17 * 17 square formations.
6. the pressurized-water reactor nuclear power plant reactor fuel assembly material-changing method as described in claim 1-3 any one, is characterized in that, in follow-up circulation, described fuel assembly adopts 1/4 Rotational Symmetry arrangement.
7. pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method as claimed in claim 6, it is characterized in that, described reactor fuel arrangement of components mode is on the basis of head circulation, by the core loading fuel management performance parameter to follow-up circulation and neutronics parameter search, forms.
8. pressurized-water reactor nuclear power plant reactor core fuel assembly material-changing method as claimed in claim 7, is characterized in that, described fuel management performance parameter comprises length of the cycle, moderator temperature coefficient, maximum radial power peak factor and maximum hot spot factor; Described neutronics parameter comprises moderator bulkfactor, Doppler temperature coefficient, Doppler power coefficient, delayed neutron fraction and prompt neutron life-span.
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| CN2007100773512A Division CN101241772B (en) | 2007-09-26 | 2007-09-26 | 18-month feed replacement method for 1-million kW unit of China PWR nuclear power station |
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|---|---|---|---|---|
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| CN102842345A (en) * | 2012-09-14 | 2012-12-26 | 南华大学 | Application of technetium-99 as burnable poison element |
| CN103000232B (en) * | 2012-12-05 | 2015-07-29 | 中国核电工程有限公司 | The head of a kind of advanced person circulates stowage of reloading for 18 months |
| CN103870615A (en) * | 2012-12-11 | 2014-06-18 | 苏州热工研究院有限公司 | Periodic demonstration method of longer-period material-changing renovation equipment from nuclear power station |
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| 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 |
| CN109359433B (en) * | 2018-12-04 | 2022-08-30 | 中国核动力研究设计院 | Automation method for reactor core refueling design |
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| CN113935567B (en) * | 2021-08-27 | 2024-01-16 | 中核龙原科技有限公司 | Quantitative evaluation method for fuel economy loss of early shutdown refueling of nuclear power plant |
| CN114242272B (en) * | 2021-12-17 | 2024-01-30 | 中国核动力研究设计院 | Small-sized nuclear power supply is with not reloading reactor core |
| CN115424747B (en) * | 2022-07-20 | 2024-01-23 | 上海核工程研究设计院股份有限公司 | Core loading scheme local search method and system |
| CN115274163B (en) * | 2022-08-05 | 2024-02-13 | 中国核动力研究设计院 | Fuel assembly management method for reactor core of pressurized water reactor nuclear power plant |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5359634A (en) * | 1992-09-30 | 1994-10-25 | Abb Atom Ab | Reactor core for a boiling water nuclear reactor |
| CN1790552A (en) * | 2004-12-16 | 2006-06-21 | 中国核动力研究设计院 | Fuel assembly changing, loading and unloading process for straight-moving nuclear reactor |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4161486B2 (en) * | 1999-10-26 | 2008-10-08 | 株式会社日立製作所 | Initial loading core of boiling water reactor |
-
2007
- 2007-09-26 CN CN201110234207.1A patent/CN102332315B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5359634A (en) * | 1992-09-30 | 1994-10-25 | Abb Atom Ab | Reactor core for a boiling water nuclear reactor |
| CN1790552A (en) * | 2004-12-16 | 2006-06-21 | 中国核动力研究设计院 | Fuel assembly changing, loading and unloading process for straight-moving nuclear reactor |
Non-Patent Citations (11)
| Title |
|---|
| CNP1500堆芯燃料管理设计;李冬生;《核动力工程》;20060831;第27卷(第4期);正文第1页第1栏第5段到第3页第2栏第1段,图2,表3 * |
| JP特开2001-124884A 2001.05.11 |
| 大亚湾核电站第十循环堆芯换料设计;李冬生;《中国核科技报告》;20040630(第1期);第201页第4段,第203页第2段,第204页第1段 * |
| 岭澳核电站二期18个月换料燃料管理研究;李雷 等;《核动力工程》;20051231;第26卷(第6期);正文第1页第1栏第1段第7-9行 * |
| 李冬生.CNP1500堆芯燃料管理设计.《核动力工程》.2006,第27卷(第4期),正文第1页第1栏第5段到第3页第2栏第1段,图2,表3. |
| 李冬生.大亚湾核电站第十循环堆芯换料设计.《中国核科技报告》.2004,(第1期),第201页第4段，第203页第2段，第204页第1段. |
| 李雷 等.岭澳核电站二期18个月换料燃料管理研究.《核动力工程》.2005,第26卷(第6期),正文第1栏第1段第7-9行. |
| 核电厂反应堆换料安全评价原理与应用;章宗耀 等;《核动力工程》;19971231;第18卷(第6期);第481页第3-4段,第482-485页 * |
| 秦山核电二期工程反应堆及反应堆冷却剂***设计;闵元佑 等;《核动力工程》;20030630;第24卷(第2期);第1-7页 * |
| 章宗耀 等.核电厂反应堆换料安全评价原理与应用.《核动力工程》.1997,第18卷(第6期),第481页第3-4段，第482-485页，表1. |
| 闵元佑 等.秦山核电二期工程反应堆及反应堆冷却剂***设计.《核动力工程》.2003,第24卷(第2期),1-7. |
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