CN101241772B - 18-month feed replacement method for 1-million kW unit of China PWR nuclear power station - Google Patents
18-month feed replacement method for 1-million kW unit of China PWR nuclear power station Download PDFInfo
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- CN101241772B CN101241772B CN2007100773512A CN200710077351A CN101241772B CN 101241772 B CN101241772 B CN 101241772B CN 2007100773512 A CN2007100773512 A CN 2007100773512A CN 200710077351 A CN200710077351 A CN 200710077351A CN 101241772 B CN101241772 B CN 101241772B
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Abstract
The present invention is suitable for stack core fuel management field of pressureized water reactor, provides a method for changing fuel of million kilowatt machine set of Chinese pressureized water reactor nuclear power plant for eighteen months. The method includes the steps as follows: in the first circulation, improving the enrichment degree of original reactor core fuel component, and changing arrangement mode of burnable poison, as well as reaching a circulation length of eighteen mouths during the first circulation; in the behind circulation, to improve the enrichment degree of the fuel component further from the second circulation, and transferring into a balance circulation rapidly, by means of changing fuel for each eighteen mouths, and only changing fuel component of one second to one third reactor core, and placing new fuel component within the reactor core, the burn-up fuel component is placed outside the reactor core. The method implements a circulation length of 473 equivalent days at full capacity, and prolongs circulation period and improves fuel consumption, as well as implements completely low neutron leakage load in the behind circulation, and has quite supernal economical efficiency and working flexibility.
Description
Technical field
The invention belongs to pressurized water reactor core fuel management field, relate in particular to 18 months material-changing methods of 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 the reactor fuel assembly and be divided into 3 enrichment regions according to the enrichment difference, the fuel assembly that 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 the reactor core inner region in the mode of chessboard.Normally year reloads when reloading, reload at every turn and change 1/3 reactor fuel assembly, the fuel assembly that burnup is the darkest is taken away, and novel fuel assembly is put into outskirt, all the other the burnup fuel assembly then rearrange at the reactor core inner region, the foundation that rearranges is to make reactor core as far as possible radially distribute power is even.
This traditional core loading pattern, the initial core fuel assembly enrichment in the 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 it is not fine that fuel utilizes economy.And adopting the loading pattern of OUT-IN when in follow-up circulation, reloading, the shortcoming of this loading pattern is because novel fuel assembly is arranged in the reactor core outskirt and causes neutron leakage rate height, thereby to such an extent as to makes the pressure vessel life-span reduce the life-span that has influenced whole nuclear power station.
Summary of the invention
The purpose of the embodiment of the invention is to provide Chinese pressurized-water reactor nuclear power plant gigawatt unit 18 months material-changing methods, 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 the fuel assembly cycle period is short, burnup is low.
The embodiment of the invention is achieved in that 18 months material-changing methods of Chinese pressurized-water reactor nuclear power plant gigawatt unit, and described method comprises the steps:
In the first circulation, improve the enrichment of initial core fuel assembly, change the arrangement of burnable poison, reach 18 months length of the cycle in the head circulation, in the first circulation, the enrichment of first reactor fuel assembly is respectively 3.9%, 3.1% and 2.0%;
In the follow-up circulation, further improve the enrichment of fuel assembly since second circulation, carry out the transition to the balance circulation fast, adopt and reloaded in 18 months, change the fuel assembly of 1/2～1/3 reactor core at every turn, and take the loading pattern of IN-OUT, novel fuel assembly is placed the reactor core inner region, the fuel assembly crossed of burnup places the reactor core outskirt, realizes that low the leakage load, and improves fuel economy.
The embodiment of the invention adopts 18 months material-changing methods of above-mentioned Chinese pressurized-water reactor nuclear power plant gigawatt unit, makes first circulation realize the length of the cycle of 473 equivalent full power days, has prolonged cycle period; Realize lower power peak factor, satisfied the world security criterion; Improved burnup, in follow-up circulation, realized low fully neutron leakage loading, quite high economy and operational flexibility have been arranged.
Description of drawings
Fig. 1 is the synoptic diagram of first circulation reactor fuel arrangement of components in 18 months material-changing methods of the Chinese pressurized-water reactor nuclear power plant gigawatt unit that provides of the embodiment of the invention, and it expresses the layout of 1/4th reactor cores;
Fig. 2 is the synoptic diagram of balance circulation reactor fuel arrangement of components in 18 months material-changing methods of the Chinese pressurized-water reactor nuclear power plant gigawatt unit that provides of the embodiment of the invention, and it expresses the layout of 1/4th reactor cores.
Embodiment
In order to make purpose of the present invention, technical scheme and advantage clearer,, the present invention is further elaborated below in conjunction with drawings and Examples.Should be appreciated that specific embodiment described herein only in order to explanation the present invention, and be not used in qualification the present invention.
The embodiment of the invention in the first circulation, places the reactor core outskirt with the fuel assembly of high enrichment, and the fuel assembly of low enrichment is placed the reactor core inner region; In the follow-up circulation, novel fuel assembly is placed the reactor core inner region, the fuel assembly crossed of burnup places the reactor core outskirt.By improving the enrichment of fuel assembly, change the number of burnable poison, realized the low fully loading that leaks.
The pressurized-water reactor nuclear power plant reactor core is made of the AFA 3G fuel assembly of 157 groups of full M5 materials, and reactor fuel active section height is 365.76cm, and equivalent diameter 304.04cm, ratio of height to diameter are 1.203.Each full M5AFA 3G 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, first circulation (first circulation) reactor fuel assembly all is a New Parent, presses
235The enrichment difference of U is divided into three enrichment regions.The enrichment of three enrichment regions can be respectively 2.0%, 3.1% and 3.9%, and the 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 the reactor core outskirt, and the lower fuel assembly of other two kinds of enrichments is arranged in the reactor core inner region by checkerboard type, and promptly 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 synoptic diagram of first circulation reactor fuel arrangement of components in 18 months material-changing methods of the Chinese pressurized-water reactor nuclear power plant gigawatt unit that provides of the embodiment of the invention, follow 1/4 rotation symmetry because the fuel assembly of full reactor core is arranged, only provided the layout of 1/4th reactor cores among the figure; Wherein n represents the number of burnable poison rod.
Horizontal ordinate is arranged by A-H successively from the outer ring to inner lane, ordinate is arranged by 08-15 to the outer ring successively from inner lane, puts in the position of H15, the G15 of reactor core, G14, F14, E14, H13, E13, D13, C12, C11, B11, B10, B09, A09, C08, A08
235The U enrichment is 3.9% fuel assembly, wherein puts fuel assembly in the position of coordinate G14, H13, E13, C11, B09, C08 and contains 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
235The U enrichment is 3.1% fuel assembly, and wherein the fuel assembly of 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
235The U enrichment is 2.0% fuel assembly, wherein the fuel assembly of 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 the reactor fuel assembly need reload, utilize the novel fuel assembly of band burnable poison rod to remove to replace the fuel assembly that burnup is crossed, and further improve
235The U enrichment.In the embodiment of the invention, can in second and third circulation, utilize
235The U 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.Be recycled to the 6th circulation, all utilizations from the 4th
235The U 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 first round-robin basis, draws by follow-up round-robin core loading searched for.Core loading search is under the prerequisite of basic security criterion, has taken all factors into consideration that fuel management performance parameter and neutronics parameter draw.Concrete fuel management result of calculation as shown in Table 2, neutronics calculation of parameter result is as shown in Table 3.
Table two
Table three
In embodiments of the present invention, balance recycles
235The U enrichment is that 68 groups of full M5 AFA3G fuel assemblies of 4.45% remove to replace burnup assembly.The reactor fuel arrangement of components adopts the low fully IN-OUT of leakage load mode in the balance circulation, be that novel fuel assembly places the reactor core inner region, the part assembly of burnup is placed on the reactor core outskirt, thereby reduces the leakage of neutron, the utilization factor of raising neutron, reaches the purpose that increases circulatory life-time.
Fig. 2 is the synoptic diagram of balance circulation reactor fuel arrangement of components in 18 months material-changing methods of the Chinese pressurized-water reactor nuclear power plant gigawatt unit that provides of the embodiment of the invention, and it expresses the layout of 1/4th reactor cores.
Horizontal ordinate is arranged by A-H successively from the outer ring to inner lane, ordinate is arranged by 08-15 to the 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 then piled and is put the old fuel assembly that burnup is crossed, and makes up with letter and number among the figure and represents the position of old fuel assembly in a last circulation of burnup.Represent that as H10 the position of this old fuel assembly in a last circulation is H10.
In embodiments of the present invention, arrange the low neutron leakage IN-OUT load mode of all employings from balance circulation reactor reloading pattern, every batch the assembly enrichment that reloads is 4.45%, and balance circulation reactor reloading pattern component count is 68 groups, and length of the cycle can reach 480EFPD.
More than just the core loading scheme satisfy basic design parameters: FDH≤1.55; FQ≤2.45 and basic security criterion, the power peak factor that obtains is quite low, and for thermal technology's safety analysis provides enough allowances, wherein FDH is an enthalpy rise factor, and FQ is a hot spot factor.In follow-up round-robin core loading scheme, improved design parameter according to international standard: FDH≤1.65; FQ≤2.45, the enrichment of the assembly that will reload simultaneously brings up to 4.45%, and the accident of secondary circuit is carried out the evaluation and the analysis of system, determines that the change of fuel management is very little to the crash analysis influence of secondary circuit.Result of calculation from table two and table three can draw this design proposal and satisfy the world security criterion fully.
18 months material-changing methods of embodiment of the invention China's pressurized-water reactor nuclear power plant gigawatt unit, in the 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 the prior art all be reload in year (about 330EFPD) compare, prolonged cycle period, improved burnup; In the follow-up circulation, further improve the enrichment of fuel assembly, carry out the transition to the balance circulation fast, adopt and reloaded in 18 months, each fuel assembly of changing 1/2～1/3 reactor core, and novel fuel assembly placed the reactor core inner region, the fuel assembly crossed of burnup places the reactor core outskirt, realized low fully neutron leakage loading, quite high economy and operational flexibility have been arranged.
The above only is preferred embodiment of the present invention, not in order to restriction the present invention, all any modifications of being done within the spirit and principles in the present invention, is equal to and replaces and improvement etc., all should be included within protection scope of the present invention.
Claims (4)
1. 18 months material-changing methods of Chinese pressurized-water reactor nuclear power plant gigawatt unit is characterized in that described method comprises the steps:
In the first circulation, improve the enrichment of initial core fuel assembly, change the arrangement of burnable poison, reach 18 months length of the cycle in the head circulation, in the first circulation, the enrichment of first reactor fuel assembly is respectively 3.9%, 3.1% and 2.0%;
In the follow-up circulation,, carry out the transition to the balance circulation fast since the further enrichment that improves fuel assembly of second circulation, adopt and reloaded in 18 months, each fuel assembly of changing 1/2～1/3 reactor core, and novel fuel assembly placed the reactor core inner region, the fuel assembly crossed of burnup places the reactor core outskirt.
2. the method for claim 1 is characterized in that, in the first circulation, adds 8,12,16 burnable poison rods of fuel assembly band of burnable poison.
3. the method for claim 1 is characterized in that, in the follow-up circulation, the enrichment of described novel fuel assembly is 4.45%.
4. the method for claim 1 is characterized in that, described follow-up circulation is transition cycles and balance circulation.
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| Application Number | Priority Date | Filing Date | Title |
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| CN2007100773512A 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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| CN2007100773512A 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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| CN201110234207.1A Division CN102332315B (en) | 2007-09-26 | 2007-09-26 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
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| CN101241772B true CN101241772B (en) | 2011-07-27 |
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|---|---|---|---|---|
| RU2524162C2 (en) * | 2009-07-31 | 2014-07-27 | Токио Инститьют Оф Текнолоджи | Nuclear reactor core and nuclear reactor |
| US9576688B2 (en) * | 2009-09-23 | 2017-02-21 | Terrapower, Llc | Movement of materials in a nuclear reactor |
| CN102054538B (en) * | 2009-10-30 | 2013-07-17 | 中国广东核电集团有限公司 | Pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and safety analysis system thereof |
| CN103474101B (en) * | 2012-06-08 | 2017-02-01 | 中国核动力研究设计院 | Nuclear reactor core arrangement of nuclear power station |
| CN103871528B (en) * | 2012-12-14 | 2017-04-05 | 中国核动力研究设计院 | A kind of long period fuel management method of pressurized water reactor core |
| CN103151084B (en) * | 2013-02-21 | 2016-02-03 | 中科华核电技术研究院有限公司 | A kind of pressurized water reactor core and New Parent thereof reload stowage |
| CN103400619B (en) * | 2013-07-03 | 2016-05-04 | 中国核电工程有限公司 | The stowage of reloading in a kind of advanced person's 1/4 reactor core year |
| 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 |
| US10593436B2 (en) | 2013-11-21 | 2020-03-17 | Terrapower, Llc | Method and system for generating a nuclear reactor core loading distribution |
| 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 |
| CN107863165B (en) * | 2017-12-08 | 2019-12-24 | 中国核动力研究设计院 | Method for loading 18-month refueling multi-cycle fuel of pressurized water 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 |
| 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 |
| CN108735308A (en) * | 2018-03-27 | 2018-11-02 | 江苏核电有限公司 | A kind of for the first time physical start-up method of the presurized water reactor without additional neutron source |
| CN111584106B (en) * | 2020-04-17 | 2022-04-19 | 岭东核电有限公司 | Nuclear power station fuel unit substitution method, device, equipment and storage medium |
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Application publication date: 20080813 Assignee: Lingao Nuclear Power Co., Ltd. Assignor: Dayawan Nuclear Power Running Management Co., Ltd. Contract record no.: 2012440020368 Denomination of invention: 18-month feed replacement method for 1-million kW unit of China voltage water pile nucleus power station Granted publication date: 20110727 License type: Exclusive License Record date: 20121212 |
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