CN105139901A - Fuel management method of pressurized water reactor core formed by 177 fuel assemblies - Google Patents

Fuel management method of pressurized water reactor core formed by 177 fuel assemblies Download PDF

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CN105139901A
CN105139901A CN201510397893.2A CN201510397893A CN105139901A CN 105139901 A CN105139901 A CN 105139901A CN 201510397893 A CN201510397893 A CN 201510397893A CN 105139901 A CN105139901 A CN 105139901A
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fuel
reactor core
fuel assembly
circulation
enrichment
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刘启伟
李庆
陈长
周金满
吴磊
李向阳
于颖锐
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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Abstract

The invention discloses a fuel management method of a pressurized water reactor core formed by 177 fuel assemblies. The method comprises the following steps: in the first cycle, fuel assemblies with three different enrichment degrees are adopted, the fuel assemblies are arranged in a high-leakage loading mode, and the cycle length of the first cycle is designed to be annual reloading; in the second cycle, the enrichment degree of reloaded new fuel assemblies is between that of the fuel assemblies in the first cycle and that of balance cycle new fuels; the enrichment degree of the reloaded new fuel assemblies is same to or greater than that of the second cycle new fuels from the third cycle to balance cycle in order to realize 18-months long cycle reloading design; and from the second cycle, core loading adopts a low-leakage loading mode. The method smoothly realizes transition of first cycle annular reloading to balance cycle 18-months long cycle reloading, guarantees the core safety of the first cycle, fast transmits to long cycle reloading design, and improves the utilization rate and the load factor of a power plant.

Description

A kind of fuel management method of the pressurized water reactor core be made up of 177 fuel assemblies
Technical field
The present invention relates to field pressurized water reactor core fuel management technical field, particularly, relate to a kind of fuel management method of the pressurized water reactor core be made up of 177 fuel assemblies, be used to guide the determination of the fuel enrichment of pressurized-water reactor nuclear power plant reactor, the selection of burnable poison and assembly and arrange at heap in-core.
Background technology
Pressurized water reactor core fuel management, refer generally to be recycled to balanced recycle reactor core (usual reactor core experiences 5 or 6 fuel recycles just reach equilibrium state) from head, determine that the type of fuel enrichment that reactor core uses, burnable poison and various assembly and poisonous substance are in the layout etc. of heap in-core, make the design result of reactor core meet core design criteria and power plant's general requirement.The quality of in-core fuel management directly affects economy and the security of nuclear power plant, is the basis of Subsequent secure analysis or evaluation.
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, namely reactor fuel assembly is divided into three 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, the fuel assembly that other two kinds of enrichments are told somebody what one's real intentions are is arranged in reactor core inner region in the mode of chessboard, when reloading, normally year reloads, reload the reactor fuel assembly of replacing 1/3 ~ 1/2 at every turn, fuel assembly the darkest for burnup is taken away, novel fuel assembly puts into outskirt, all the other burnup fuel assembly then rearrange at reactor core inner region, as far as possible the foundation rearranged makes the radial power of reactor core be evenly distributed.
At present, domestic in-service and building the in-core fuel management method of nuclear power plant, mainly contain two types: 1) all circulations are the fuel management method of reloading in year; 2) first circulation is for reloading in year, again through argument and analysis after balanced recycle, is progressively transitioned into long period material-changing method.The feature of the above-mentioned type fuel management mainly contains: 1) described reactor core is made up of 121 or 157 fuel assemblies; 2) first two fuel management method or do not realize the requirement that long period reloads, otherwise process seems tortuous, and the New Policy of change needs to select a good opportunity after nuclear power plant's generating again to prove, and being transitioned into long circulating refueling design needs the cycle that experience is longer.
To sum up, its weak point is: the target of reloading due to the long period that could not comparatively fast realize power station, and the availability that power plant runs well does not improve, and nuclear power plant's economy also has the space optimized further.
Summary of the invention
Technical matters to be solved by this invention be to provide a kind of implementation procedure gently, not only ensure that first circulation reactor core security, but also the fuel management method of the pressurized water reactor core be made up of 177 fuel assemblies that long period reloads can be transitioned into quickly.
The present invention's adopted technical scheme that solves the problem is:
A fuel management method for the pressurized water reactor core be made up of 177 fuel assemblies, comprises the following steps:
In first circulation, fuel assembly adopts 3rd district to load, and namely adopts the fuel assembly of three kinds of different enrichments, and the arrangement of fuel assembly adopts high-leakage loading pattern, and first circulation length of the cycle is year refueling design;
In second circulation, the enrichment of the novel fuel assembly of loading be greater than fuel assembly in first circulation enrichment and be less than following cycle novel fuel assembly enrichment; Second circulation is an important transition cycles.Appropriateness improves fresh fuel enrichment, and this enrichment is between the virgin material enrichment that head circulates and following cycle adopts, and object is the reactor core length of the cycle gently increasing this circulation.Novel fuel assembly is placed in the inner ring of reactor core, and inner ring refers to the fuel region within reactor core outmost turns; Burnup crosses the outmost turns that an old assembly circulated is placed in reactor core;
Start until balanced recycle from the 3rd circulation, the enrichment that the unified employing of reactor core fresh fuel is higher, the enrichment of the novel fuel assembly of loading is identical and be greater than the enrichment of the novel fuel assembly loaded in the second circulation; Core loading utilizes low-leakage mode, namely novel fuel assembly is placed in reactor core inner ring and arranges with the assembly transpostion interval that burnup is crossed, the darker old assembly of burnup is then positioned over reactor core outmost turns, balanced recycle reactor core length of the cycle can reach 470 to 500 equivalent full power days, realizes 18 months long period refueling design;
From the second circulation, core loading all adopts low leakage load mode.
The present invention head circulation adopts year refueling design; Start from the second circulation, progressively improve the fresh fuel enrichment (between head circulation and following cycle virgin material enrichment) of loading and appropriateness increases novel fuel assembly quantity, be i.e. just progressively prolongation reactor core length of the cycle from the second circulation; Be recycled to balanced recycle from the 3rd, fresh fuel just adopts a kind of higher fuel enrichment, is progressively transitioned into the designing requirement realizing balanced recycle 18 months long periods and reload.Described pressurized water reactor core is made up of 177 fuel assemblies, the present invention is directed to 177 reactor cores, tackles key problems to the layout of fuel assembly and burnable poison, and solves technical matters to be solved by this invention by technique scheme.Described high-leakage loading pattern is the outmost turns that in the fuel assembly of three kinds of different enrichments that reactor core adopts, the highest fuel assembly of enrichment is arranged in reactor core, and the inside that the fuel assembly of remaining two kinds of enrichment is then arranged in reactor core is arranged in intersecting checkerboard type.
Described low leakage load mode is that each novel fuel assembly loaded all is arranged in reactor core inner region, the fuel assembly that burnup has been crossed is arranged in reactor core outskirt, namely each novel fuel assembly loaded is placed in reactor core inner lane, the old assembly that burnup is crossed is placed in reactor core outer ring, refer to further: the great majority in the novel fuel assembly at every turn added are placed in the secondary outer ring of reactor core, a part is placed on the more inner position of reactor core, reactor core outmost turns places the old assembly that the comparatively dark or burnup of burnup crosses multiple circulation, the old assembly that the burnup of reactor core inner lane is crossed and the mutual matched combined of New Parent, or the assembly making burnup cross is intersection arrangement mode by the difference of burn-up level
In order to control initial core built-in reactivity, extend core life and flatten core power distribution better, in fuel assembly guide pipe, put into the Pyrex burnable poison rod of varying number or carried gadolinia fuel rod, according to core power distribution and the reactive requirement controlled, the solid combustible poison rod that reasonable Arrangement reactor core adopts is at the modes of emplacement of heap in-core.Contain Pyrex burnable poison rod in first circulation in fuel assembly or carry gadolinia fuel rod, from the second circulation, containing a year gadolinia fuel rod in the novel fuel assembly of loading.
In first circulation, in fuel assembly, the radical of Pyrex burnable poison rod or year gadolinia fuel rod is 8,12,16,20 or 24;
From the second circulation, the radical carrying gadolinia fuel rod in the novel fuel assembly of loading is 12,16 or 20.
The described gadolinia fuel rod that carries is formed for being evenly mixed in pellet by integrated Gd burnable poison, the existence form UO of gadolinium in integrated Gd burnable poison 2-Gd 2o 3.
Preferably, each fuel assembly changing 1/3 ~ 1/2 reactor core from the second circulation.
In first circulation, adopt three kinds of differences and have the fuel assembly of certain gradient enrichment, the enrichment of described three kinds is three kinds arbitrarily in 1.8%, 2.4%, 3.1%, 3.7%, 3.9% with certain gradient
The enrichment of the novel fuel assembly loaded from the 3rd circulation is the 4.45%, second enrichment circulating the novel fuel assembly loaded is 3.9%; Or the enrichment of novel fuel assembly loaded from the 3rd circulation be the enrichment of the novel fuel assembly that the 4.95%, second circulation loads is 4.2% or 4.45%.
To sum up, the invention has the beneficial effects as follows:
1, fuel management method provided by the invention, method achieves to circulate to reload in year from head and is transitioned into the technical need of balanced recycle 18 months long period refueling design, is applicable to the pressurized water reactor core be made up of 177 fuel assemblies.The process that the method realizes is mild, both ensure that the security of first circulation reactor core, and can be transitioned into again the design that long period reloads quickly, improve availability and the stressor of power plant.
2, the second circulation in the present invention is an important transition cycles, this circulation novel fuel assembly enrichment have employed a value between head circulation and balanced recycle fresh fuel, make whole transition relatively milder, take into account the difficult point flattening core power distribution and the cost-effectiveness requirement promoting reactor core length of the cycle.
3, the present invention is recycled to balanced recycle from the 3rd, and reactor core length of the cycle reaches 18 months long period refueling design substantially, can reach the length of the cycle of 470 to 500 equivalent full power days.
Accompanying drawing explanation
Fig. 1 is that the one of the first circulation reactor core of the present invention loads schematic diagram;
Fig. 2 is the one loading schematic diagram that the present invention second is recycled to balanced recycle reactor core.
Embodiment
Below in conjunction with embodiment and accompanying drawing, to the detailed description further of the present invention's do, but embodiments of the present invention are not limited thereto.
Embodiment:
The present embodiment is for a million kilowatt nuclear power factory reactor core, and this reactor core is made up of 177 fuel assemblies.The fuel management of complete nuclear power plant's reactor core, should according to set target and given reactor core parameter restrictive condition or criterion, plan as a whole the core loading pattern determining a series of reactor fuel circulations being recycled to balanced recycle from head, the neutronics of line correlation of going forward side by side calculates.Particular content is contained: the layout of the selection of the determination of the first several different fuel enrichments adopted that circulate, the determination of following cycle novel fuel assembly enrichment, the solid combustible poisonous substance type of each circulation, reactor fuel assembly and solid combustible poisonous substance and optimization, preliminary safety evaluation etc.
Circulate to head the loading of reactor core, adopts three kinds of differences and have the fuel assembly of certain gradient enrichment.Selectable fresh fuel enrichment type, comprising: 1.8%, 2.4%, 3.1%, 3.7%, 3.9% etc.Consider that used whole of first circulation are novel fuel assembly, therefore the loading pattern of the arrangement of assembly employing high-leakage.Fig. 1 gives the loading schematic diagram of a typical first circulation reactor core, fuel assembly due to Whole core is arranged and is followed 1/4 Rotational Symmetry, the layout of 1/4th reactor cores is only gived in figure, horizontal ordinate is arranged by A-H from outer ring successively to inner lane, ordinate is arranged by 08-15 from inner lane successively to outer ring, square in figure represents fuel assembly, in square, filled black density its enrichment larger is lower, such as square B11, square C11, the enrichment size order of the fuel assembly representated by square D11 is B11>C11>D11, the quantity of the burnable poison rod contained by numeral fuel assembly in square, such as, numeral " 20 " representative in square B11: containing 20 burnable poison rods in the fuel assembly representated by square B11, numeral " 16 " representative in square A08: containing 20 burnable poison rods in the fuel assembly representated by square A08.The fuel assembly that in the fuel assembly of three kinds of different enrichments that reactor core adopts, enrichment is the highest is arranged in the outmost turns of reactor core, and the fuel assembly of remaining two kinds of enrichment is then arranged in the inside of reactor core in intersecting checkerboard type layout.
In order to control initial core built-in reactivity, extend core life and flatten core power distribution better, in fuel assembly guide pipe, put into the Pyrex burnable poison rod of varying number, or adopt integrated Gd burnable poison, its form is UO 2-Gd 2o 3be evenly mixed in pellet to be formed and carry gadolinia fuel rod.Described fuel assembly can arrange that 8,12,16,20 and 24 Pyrex poison rods or year gadolinia fuel are excellent.
Above-mentioned first circulation core loading pattern, length of the cycle is year refueling design.
For the design of the second circulation, the enrichment that novel fuel assembly uses adopts between enrichment size between the institute of head circulation and following cycle novel fuel assembly, the enrichment of the novel fuel assembly namely loaded be greater than head circulate in fuel assembly enrichment and be less than following cycle novel fuel assembly enrichment.Such design can make transition relatively milder, has taken into account the technological difficulties flattening core power distribution and the technical requirement increasing reactor core length of the cycle.If following cycle virgin material enrichment adopt 4.45%, then second circulation can use enrichment be 3.9% fresh fuel; If the enrichment that following cycle virgin material adopts is 4.95%, then the second circulation virgin material enrichment can select 4.2% or 4.45%.
Novel fuel assembly is placed in the inner ring of reactor core, and inner ring refers to the fuel region within reactor core outmost turns; Burnup crosses the outmost turns that an old assembly circulated is placed in reactor core.
Be recycled to balanced recycle from the 3rd, the fuel enrichment that virgin material adopts is identical and that circulate than second large; Core loading utilizes low-leakage mode, namely novel fuel assembly is placed in reactor core inner ring and arranges with the assembly transpostion interval that burnup is crossed, the darker old assembly of burnup is then positioned over reactor core outmost turns, and balanced recycle reactor core length of the cycle reaches the requirement of 18 months long circulating refueling design.
From the second circulation, core loading all adopts low leakage way, Fig. 2 gives one is recycled to balanced recycle typical case reactor core loading schematic diagram from second, fuel assembly due to Whole core is arranged and is followed 1/4 Rotational Symmetry, the layout of 1/4th reactor cores is only gived in figure, horizontal ordinate is arranged by A-H from outer ring successively to inner lane, ordinate is arranged by 08-15 from inner lane successively to outer ring, square in figure represents fuel assembly, the square of figure empty represents novel fuel assembly, such as square F08, square E11 etc., the quantity of the burnable poison rod contained by numeral fuel assembly in square, such as, numeral " 12 " representative in square B10: containing 12 burnable poison rods in the novel fuel assembly representated by square B10, numeral " 16 " representative in square B08 and square B09: all containing 16 burnable poison rods in square B08 and the novel fuel assembly representated by square B09.As shown in Figure 2, the great majority in the novel fuel assembly at every turn added are placed in the secondary outer ring of reactor core, and a part is placed on the more inner position of reactor core.Reactor core outmost turns places the old assembly that the comparatively dark or burnup of burnup crosses multiple circulation.The old assembly that the burnup of reactor core inner lane is crossed and the mutual matched combined of New Parent, or the assembly that burnup is crossed by the difference of burn-up level in intersecting arrangement mode.
Each fuel assembly changing 1/3 ~ 1/2 reactor core from the second circulation, solid combustible poisonous substance uses gadolinium, and its form is UO 2-Gd 2o 3be evenly mixed in pellet to be formed and carry gadolinia fuel rod.The typical amounts that described invention following cycle novel fuel assembly band carries gadolinia fuel rod is 12,16 or 20.
Adopt in-core fuel management method of the present invention, from head circulation year refueling design gradually gentle transition to 18 months long period refueling design (length of the cycle can reach 470 to 500 equivalent full power days) of balanced recycle, take into account the length of the cycle that core power distribution turn increases following cycle reactor core simultaneously, promote the utilization factor of nuclear fuel and the performance driving economy of power plant.
To sum up, the invention discloses a kind of fuel management method of the pressurized water reactor core be made up of 177 fuel assemblies, achieve reactor and to circulate the technological means that 18 months long periods that year refueling design is transitioned into balanced recycle reload from head.First circulation reactor core adopts high-leakage loading pattern, and fuel assembly can adopt 3 kinds of enrichments do not waited, and wherein the highest enrichment assembly is placed on the outmost turns of reactor core, arranges in heap core inner submission fork checkerboard type compared with the fuel assembly of low enrichment.First circulation reactor core solid combustible poisonous substance adopts Pyrex or carries gadolinia fuel rod, can according to the needs flattening core power distribution, and fuel used assembly can arrange 8,12,16,20 or 24 poison rods.Following cycle adopts low leakage loading pattern, and the novel fuel assembly of use of at every turn reloading is placed in the inner ring of reactor core, and reactor core outmost turns places the old assembly that burnup is crossed.Especially, the second fresh fuel enrichment recycled between head circulation and following cycle novel fuel assembly enrichment between, the 3rd be recycled to balanced recycle fresh fuel enrichment identical and higher than second circulation.Following cycle New Parent adopts integration to carry Gd burnable poison fuel rod, the quantity of layout be 12,16 or 20 not etc.Technical scheme of the present invention, especially for the reactor core be made up of 177 fuel assemblies, achieve and be progressively transitioned into 18 months long period refueling design of balanced recycle from the head year refueling design that circulates, balanced recycle length can reach 470 to 500 equivalent full power days.This technical method has taken into account the length of the cycle that core power distribution turn increases following cycle reactor core simultaneously, ensure that reactor core safety in operation, improves again the utilization factor of nuclear fuel and the performance driving economy of power plant.

Claims (8)

1. a fuel management method for the pressurized water reactor core be made up of 177 fuel assemblies, is characterized in that, comprise the following steps:
In first circulation, adopt the fuel assembly of three kinds of different enrichments, the arrangement of fuel assembly adopts high-leakage loading pattern, and first circulation length of the cycle is year refueling design;
In second circulation, the enrichment of the novel fuel assembly of loading be greater than fuel assembly in first circulation enrichment and be less than following cycle novel fuel assembly enrichment;
Until balanced recycle from the 3rd circulation, the enrichment of the novel fuel assembly of loading is identical and be greater than the enrichment of the novel fuel assembly loaded in the second circulation; Balanced recycle reactor core length of the cycle can reach 470 to 500 equivalent full power days, realizes 18 months long period refueling design;
From the second circulation, core loading all adopts low leakage load mode.
2. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 1, it is characterized in that, described high-leakage loading pattern is the outmost turns that in the fuel assembly of three kinds of different enrichments that reactor core adopts, the highest fuel assembly of enrichment is arranged in reactor core, and the inside that the fuel assembly of remaining two kinds of enrichment is then arranged in reactor core is arranged in intersecting checkerboard type.
3. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 1, it is characterized in that, described low leakage load mode is that each novel fuel assembly loaded all is arranged in reactor core inner region, and the fuel assembly that burnup has been crossed is arranged in reactor core outskirt.
4. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 1, it is characterized in that, contain Pyrex burnable poison rod in first circulation in fuel assembly or carry gadolinia fuel rod, from the second circulation, containing carrying gadolinia fuel rod in the novel fuel assembly of loading.
5. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 4, it is characterized in that, in first circulation, in fuel assembly, the radical of Pyrex burnable poison rod or year gadolinia fuel rod is 8,12,16,20 or 24;
From the second circulation, the radical carrying gadolinia fuel rod in the novel fuel assembly of loading is 12,16 or 20.
6. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 4 or 5, it is characterized in that, the described gadolinia fuel rod that carries is formed for being evenly mixed in pellet by integrated Gd burnable poison, the existence form UO of gadolinium in integrated Gd burnable poison 2-Gd 2o 3.
7. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 1, it is characterized in that, in first circulation, adopt three kinds of differences and have the fuel assembly of certain gradient enrichment, the enrichment of described three kinds is three kinds arbitrarily in 1.8%, 2.4%, 3.1%, 3.7%, 3.9% with certain gradient.
8. the fuel management method of a kind of pressurized water reactor core be made up of 177 fuel assemblies according to claim 1, it is characterized in that, the enrichment of the novel fuel assembly loaded from the 3rd circulation is the 4.45%, second enrichment circulating the novel fuel assembly loaded is 3.9%; Or the enrichment of novel fuel assembly loaded from the 3rd circulation be the enrichment of the novel fuel assembly that the 4.95%, second circulation loads is 4.2% or 4.45%.
CN201510397893.2A 2015-07-09 2015-07-09 Fuel management method of pressurized water reactor core formed by 177 fuel assemblies Pending CN105139901A (en)

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CN106384612A (en) * 2016-10-31 2017-02-08 中广核研究院有限公司 High-flexibility fuel management method
CN107068211A (en) * 2017-02-28 2017-08-18 中国核动力研究设计院 A kind of method that use postdose fuel element substitutes a neutron source
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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
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CN108053904A (en) * 2017-12-08 2018-05-18 中国核动力研究设计院 A kind of 18 months stowages of reloading of the first Xun Huan reactor core containing gadolinium of presurized water reactor
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CN113823427A (en) * 2021-09-17 2021-12-21 山东核电有限公司 Method for managing fuel in pressurized water reactor core with flexibly adjusted cycle length
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CN106384612B (en) * 2016-10-31 2018-06-26 中广核研究院有限公司 A kind of fuel management method with high flexibility
JP2020508463A (en) * 2017-02-27 2020-03-19 テラパワー, エルエルシー System and method for modeling a nuclear reactor
JP2022111366A (en) * 2017-02-27 2022-07-29 テラパワー, エルエルシー System and method for modeling nuclear reactor
JP7090096B2 (en) 2017-02-27 2022-06-23 テラパワー, エルエルシー Systems and methods for modeling nuclear reactors
CN107068211A (en) * 2017-02-28 2017-08-18 中国核动力研究设计院 A kind of method that use postdose fuel element substitutes a neutron source
CN107093478A (en) * 2017-03-30 2017-08-25 中国核电工程有限公司 A kind of pressurized water reactor core balanced recycle material-changing method of 24 months
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
CN107093480A (en) * 2017-03-30 2017-08-25 中国核电工程有限公司 A kind of alternate reactor fuel of phase in presurized water reactor longevity length reloads stowage
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CN107910077A (en) * 2017-10-19 2018-04-13 中国核电工程有限公司 A kind of core loading method of the alternate balanced recycle of VVER heap-type length
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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
CN108053904A (en) * 2017-12-08 2018-05-18 中国核动力研究设计院 A kind of 18 months stowages of reloading of the first Xun Huan reactor core containing gadolinium of presurized water reactor
CN109994233B (en) * 2019-04-08 2022-02-22 中国核动力研究设计院 Partial low-leakage loading and reloading method suitable for modular mini-stack
CN109994233A (en) * 2019-04-08 2019-07-09 中国核动力研究设计院 A kind of low leakage in part suitable for the small-sized heap of modular loads material-changing method
CN110136848A (en) * 2019-05-21 2019-08-16 中国核动力研究设计院 High temperature nuclear reactor reactor core of the passive discharge fuel sphere as second set of reactor shut-off system
CN110136848B (en) * 2019-05-21 2020-08-04 中国核动力研究设计院 High-temperature reactor core taking passive discharged fuel spheres as second shutdown system
CN111584107A (en) * 2020-04-17 2020-08-25 岭东核电有限公司 Recombination substitution method, device, equipment and storage medium for fuel unit of nuclear power station
CN111584107B (en) * 2020-04-17 2022-04-19 岭东核电有限公司 Recombination substitution method, device, equipment and storage medium for fuel unit of nuclear power station
CN111899899A (en) * 2020-08-12 2020-11-06 中国核动力研究设计院 Method for reducing HFETR reactor core nonuniformity
CN111899899B (en) * 2020-08-12 2022-03-25 中国核动力研究设计院 Method for reducing HFETR reactor core nonuniformity
CN112259269A (en) * 2020-10-21 2021-01-22 中国核动力研究设计院 Loading method for 18-month cycle length of reactor core of million-kilowatt pressurized water reactor nuclear power plant
CN113823427A (en) * 2021-09-17 2021-12-21 山东核电有限公司 Method for managing fuel in pressurized water reactor core with flexibly adjusted cycle length
CN113823427B (en) * 2021-09-17 2023-09-22 山东核电有限公司 Pressurized water reactor core fuel management method with flexibly-adjusted cycle length
CN115171922A (en) * 2022-07-21 2022-10-11 中国核动力研究设计院 Method for loading low-fuel-consumption fuel assemblies in initial reactor core of pressurized water reactor
CN115171922B (en) * 2022-07-21 2024-05-07 中国核动力研究设计院 Loading method for loading low-burnup fuel assemblies into pressurized water reactor initial reactor core

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