CN103000232A - Advanced first circulation 18-month refuelling and loading method - Google Patents
Advanced first circulation 18-month refuelling and loading method Download PDFInfo
- Publication number
- CN103000232A CN103000232A CN2012105176523A CN201210517652A CN103000232A CN 103000232 A CN103000232 A CN 103000232A CN 2012105176523 A CN2012105176523 A CN 2012105176523A CN 201210517652 A CN201210517652 A CN 201210517652A CN 103000232 A CN103000232 A CN 103000232A
- Authority
- CN
- China
- Prior art keywords
- fuel
- gadolinium
- circulation
- fuel assembly
- enrichment
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to a design technology of reactors, and in particular relates to a first circulation 18-month refuelling and loading method n a reactor core of a pressurized water reactor nuclear power station. According to the method, aiming at the reactor core consisting of 177 group of fuel assemblies, in the first circulation, gadolinium-containing fuel assemblies are used as part of fuel assemblies, Gd2O3 is a combustible toxic material, Gd2O3 and UO2 in gadolinium-containing fuel rods of the gadolinium-containing fuel assemblies are mixed and uniformly dispersed in fuel core blocks, and 2%-10% of Gd2O3 is contained in the gadolinium-containing fuel core blocks by weight percent. According to the method, under the premise of meeting various safety criterions, the condition that the natural circulation length is 482 equivalent full power days is met; and compared with the conventional method of using solid combustible toxic materials of borosilicate glass in the first circulation, the method has the advantage that the circulation length is prolonged by 147 equivalent full power days and is equivalent to the balance circulation length of 18-month refueling, and is quietly high in economy and operation flexibility.
Description
Technical field
The invention belongs to the reactor designing technique, be specifically related to the first stowage of reloading in 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 formed by 177 group fuel assemblies, traditional method for arranging is: the reactor fuel assembly is divided into to 3rd district according to the difference of enrichment and arranges, the enrichment in this 3rd district is respectively 1.8%, 2.4%, 3.1%, the fuel assembly that wherein enrichment is 1.8% is not containing the solid combustible poisonous substance, may contain the solid combustible poisonous substance in the fuel assembly that enrichment is 2.4% and 3.1%, the solid combustible poisonous substance used in the head circulation is borosilicate glass.Meeting under the prerequisite of 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: technique is comparatively complicated on manufacturing, and the borosilicate glass of ring-type is contained in stainless sleeve pipe; Directly be inserted in the guide pipe position of fuel assembly with the form of burnable poison rod, and control rod is also the guide pipe position that is inserted in fuel assembly, therefore the fuel assembly that inserts burnable poison rod just can not insert control rod again, that is to say that the use of borosilicate glass burnable poison rod has limited the dirigibility of control rod design to a certain extent; In addition; after first circulation; need removal borosilicate glass burnable poison rod; carry out extra packing and processing; the solid combustible poison rod that contains 1248 borosilicate glasses in the first circulation of the reactor core that 177 group fuel assemblies form; therefore the solid combustible poison rod that the radioactive waste additionally caused is 1248 borosilicate glasses, be unfavorable for environmental protection.
Summary of the invention
The first cyclical loadings method of the reactor core that the object of the present invention is to provide a kind of 177 group fuel assemblies to form, be intended to solve the solid combustible poisonous substance that uses traditional borosilicate glass in first circulation and cause that radioactive waste is many, above dumb, length of the cycle and the balanced recycle length of reloading in 18 months differ more problem to be unfavorable for environmental protection and control rod design.
Technical scheme of the present invention is as follows: a kind of advanced person's the head stowage of reloading in 18 months that circulates, and reactor core is comprised of 177 group fuel assemblies, and in the head circulation, the part of fuel assembly is used containing the gadolinia fuel assembly, Gd
2o
3for the 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 the gadolinia fuel pellet
2o
3percentage by weight be 2%-10%.
Further, the advanced person's as above head stowage of reloading in 18 months that circulates, wherein, described 177 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, there is no gadolinium-containing fuel rod in the fuel assembly that wherein enrichment is 2.0%, in the fuel assembly that enrichment is 3.1% and 3.9%, contain gadolinium-containing fuel rod.
Further, containing 4,8,12,16,20 or 24 gadolinium-containing fuel rods containing in the gadolinia fuel assembly.
Further, the advanced person's as above head stowage of reloading in 18 months that circulates, wherein, in the fuel assembly subregion of described three kinds of enrichments, the fuel assembly that enrichment is the highest is loaded in the reactor core outskirt, and other two kinds are arranged in the reactor core inner region than the fuel assembly of low enrichment by checkerboard type.
Beneficial effect of the present invention is as follows: the present invention adopts Gd in the head circulation
2o
3as burnable poison, meeting under the prerequisite of every safety criterion, realized that Natural Circulation length is 482 equivalent full power days, with in traditional head circulation, use the solid combustible poisonous substance of borosilicate glass to compare, length of the cycle has been grown 147 equivalent full power days, suitable with the balanced recycle length of reloading in 18 months, there is quite high economy and operational flexibility.
Compare the solid combustible poisonous substance of traditional borosilicate glass, adopt Gd
2o
3the burnable poison material also have following advantage: the technique manufacture is comparatively simple, Gd
2o
3with UO
2mix disperse in fuel pellet; Do not take the guide pipe position, therefore can not interfere with the design attitude of control rod; Do not need to carry out extra processing, because Gd
2o
3reduce along with the burnup in reactor core, there is no remnants, therefore there is no radioactive waste, be conducive to environmental protection.
The accompanying drawing explanation
The arrangement schematic diagram that Fig. 1 is reactor fuel assembly in specific embodiments of the invention.
In figure,
mean
235the fuel assembly that the U enrichment is 3.9%;
□mean
235the fuel assembly that the U enrichment is 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 first circulation of the reactor core formed at 177 group fuel assemblies, use Gd
2o
3as burnable poison, improve the fuel assembly initial enrichment, rearrange the position of fuel assembly in reactor core, make the length of the cycle of first circulation reach 18 months to reload length.
The reactor core that 177 group fuel assemblies form consists 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 is arranged by 17 * 17 square formations, comprises 264 fuel rods, 24 guide pipes and 1 gauge pipe.
Contain Gd in the gadolinia fuel pellet in first circulation
2o
3percentage by weight can from 2% to 10% do not wait, as one embodiment of the present of invention, in first circulation containing Gd in the gadolinia fuel pellet
2o
3percentage by weight be 8%.
In 17 * 17 fuel assemblies, can contain 4,8,12,16,20 or 24 gadolinium rods, to design, bring larger dirigibility.In the embodiment of the present invention, it is as follows that the fuel assembly of first circulation reactor core is divided into Four types 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 the solid combustible poisonous substance, be structurally and UO
2mixing sintering are at UO
2in pellet, therefore use Gd
2o
3do not take the position of guide pipe in fuel assembly as the solid combustible poisonous substance, control rod is to insert the guide pipe position, therefore uses Gd
2o
3as the solid combustible poisonous substance, with the Position Design of control rod, do not interfere, compare the solid combustible poisonous substance of traditional use borosilicate glass and the situation that the control rod Position Design interferes, the dirigibility that has improved to the full extent the control rod Position Design; In addition, use Gd
2o
3can also realize the beginning of life moderator temperature coefficient is controlled preferably.Due to Gd
2o
3be and UO
2pellet is sintering together, do not increase the refuse amount outside spentnuclear fuel, and borosilicate glass need to carry out extra packing and processing as the inserting type assembly, can additionally cause radioactive waste.Simultaneously, Gd
2o
3manufacturing process comparatively simple easily, and the borosilicate glass burnable poison is comparatively complicated on manufacturing as the inserting type assembly.
In first circulation, the 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 the fuel stack number of packages is followed successively by 61,68 and 48 groups, in the fuel assembly that wherein enrichment is 3.1% and 3.9%, may contain gadolinium-containing fuel rod.The fuel assembly that enrichment is the highest is loaded in the reactor core outskirt, and other two kinds are arranged in the reactor core inner region than 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 that forms of 177 group fuel assemblies that the embodiment of the present invention provides, the wherein number of gadolinium-containing fuel rod in the numeral assembly in icon.
Horizontal ordinate is turned left and is arranged by A-R successively from the right side, ordinate is arranged by 1-15 from top to bottom successively, in the 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, the P08 location arrangements
235the fuel assembly that the U enrichment is 2.0%, the fuel assembly of this enrichment does not all contain gadolinium-containing fuel rod.
B 06 at 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, the P10 location arrangements
235the fuel assembly that the U enrichment is 3.1%, wherein the fuel assembly in B06, B10, F02, F14, K02, K14, P06, P10 location arrangements contains 8 gadolinium-containing fuel rods, fuel assembly in 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 contains 16 gadolinium-containing fuel rods, fuel assembly in D07, D09, E06, E10, F05, F11, G04, G08, G12, H07, H09, J04, J08, J12, K05, K11, L06, L10, M07, M09 location arrangements contains 20 gadolinium-containing fuel rods.
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 at initial core
235the fuel assembly that the U enrichment is 3.9%, wherein the fuel assembly in B05, B11, E02, E14, L02, L14, P05, P11 location arrangements contains 12 gadolinium-containing fuel rods; Fuel assembly in A08, H01, H15, R08 location arrangements contains 16 gadolinium-containing fuel rods; Fuel assembly in C04, C12, D03, D13, M03, M13, N04, N12 location arrangements contains 20 gadolinium-containing fuel rods.
The core loading optimal design arranges it is under the prerequisite of basic security criterion, has considered that fuel management performance parameter and neutronics parameter draw.As shown in Table 1, neutronics calculation of parameter result 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 calculation of parameter result
| Major parameter | Numerical value |
| Moderator bulkfactor-maximal value (10 5pcm/g/cm 3） | 0.388 |
| Doppler's temperature coefficient (absolute value maximal value) pcm/ ℃ | -4.121 |
| Doppler's temperature coefficient (absolute value minimum value) pcm/ ℃ | -1.894 |
| Doppler's power coefficient (low limit value) pcm/%FP | -6.888--5.253(0%-100%) |
| Doppler's 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 |
| The prompt neutron life-span (maximal value) | 27.657 |
Initial core loading pattern in above first 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.Result of calculation from table one and table two can show that in the first circulation of this scheme, the design proposal to novel fuel assembly meets safety criterion fully.
Obviously, those skilled in the art can carry out various changes and modification and not break away from the spirit and scope of the present invention the present invention.Like this, if of the present invention these are revised and within modification belongs to the scope of the claims in the present invention and equivalent technology thereof, the present invention also is intended to comprise these changes and modification interior.
Claims (4)
1. an advanced person the head stowage of reloading in 18 months that circulates, reactor core is comprised of 177 group fuel assemblies, it is characterized in that: in the head circulation, the part of fuel assembly is used containing the gadolinia fuel assembly, Gd
2o
3for the 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 the gadolinia fuel pellet
2o
3percentage by weight be 2%-10%.
2. the advanced person's as claimed in claim 1 head stowage of reloading in 18 months that circulates is characterized in that: described 177 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, there is no gadolinium-containing fuel rod in the fuel assembly that wherein enrichment is 2.0%, in the fuel assembly that enrichment is 3.1% and 3.9%, contain gadolinium-containing fuel rod.
3. the advanced person's as claimed in claim 2 head stowage of reloading in 18 months that circulates, is characterized in that: containing in the gadolinia fuel assembly, containing 4,8,12,16,20 or 24 gadolinium-containing fuel rods.
4. the advanced head stowage of reloading in 18 months that circulates as claimed in claim 2 or claim 3, it is characterized in that: in the fuel assembly subregion of described three kinds of enrichments, the fuel assembly that enrichment is the highest is loaded in the reactor core outskirt, and other two kinds are arranged in the reactor core inner region than the fuel assembly of low enrichment by checkerboard type.
Priority Applications (1)
| 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 |
Applications Claiming Priority (1)
| 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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103000232A true CN103000232A (en) | 2013-03-27 |
| CN103000232B CN103000232B (en) | 2015-07-29 |
Family
ID=47928701
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210517652.3A Active CN103000232B (en) | 2012-12-05 | 2012-12-05 | The head of a kind of advanced person circulates stowage of reloading for 18 months |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103000232B (en) |
Cited By (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 |
| CN103680652A (en) * | 2013-12-03 | 2014-03-26 | 中国核电工程有限公司 | Reactor core loading method with first firing cycle adopting fuel assemblies having one enrichment degree |
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
| CN104952492A (en) * | 2015-05-11 | 2015-09-30 | 中国核动力研究设计院 | Gadolinium-carrying fuel rod, fuel assembly with gadolinium-carrying fuel rods and pressurized water reactor core |
| CN105139900A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | 24-Month reload core loading method adopting erbium inflammable poison |
| CN105280256A (en) * | 2014-05-29 | 2016-01-27 | 江苏核电有限公司 | Leading fuel assembly mixing reactor core loading method |
| 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 |
| CN107863166A (en) * | 2017-12-08 | 2018-03-30 | 中国核动力研究设计院 | A kind of stowage of reloading for 18 months of the first circulation boracic reactor core of presurized water reactor |
| CN107910078A (en) * | 2017-12-08 | 2018-04-13 | 中国核动力研究设计院 | 18 months of a kind of pressurized water reactor core are reloaded the management method of multi-cycle fuel |
| CN108039216A (en) * | 2017-12-08 | 2018-05-15 | 中国核动力研究设计院 | A kind of balanced recycle of pressurized water reactor core reloads stowage for 18 months |
| 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 |
| CN113496784A (en) * | 2020-04-03 | 2021-10-12 | 华龙国际核电技术有限公司 | Reactor core of nuclear power station reactor |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62261988A (en) * | 1986-05-08 | 1987-11-14 | 株式会社東芝 | Boilint water type reactor |
| US5852645A (en) * | 1994-12-23 | 1998-12-22 | Framatome | Fuel assembly with consumable poison, and a method of operating a reactor |
| CN1781588A (en) * | 2004-12-02 | 2006-06-07 | 中国核动力研究设计院 | Material mixing process and device for preparing (U, Gd) 02 combustible poisonous core block |
| CN101226782A (en) * | 2007-10-19 | 2008-07-23 | 大亚湾核电运营管理有限责任公司 | Stowage method of million kilowatt units principal circle reactor core of Chinese press water stack nuclear power station |
| CN101572127A (en) * | 2008-04-28 | 2009-11-04 | 中科华核电技术研究院有限公司 | Nuclear fuel rod, nuclear fuel component and nuclear reactor core |
| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
-
2012
- 2012-12-05 CN CN201210517652.3A patent/CN103000232B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62261988A (en) * | 1986-05-08 | 1987-11-14 | 株式会社東芝 | Boilint water type reactor |
| US5852645A (en) * | 1994-12-23 | 1998-12-22 | Framatome | Fuel assembly with consumable poison, and a method of operating a reactor |
| CN1781588A (en) * | 2004-12-02 | 2006-06-07 | 中国核动力研究设计院 | Material mixing process and device for preparing (U, Gd) 02 combustible poisonous core block |
| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
| CN101226782A (en) * | 2007-10-19 | 2008-07-23 | 大亚湾核电运营管理有限责任公司 | Stowage method of million kilowatt units principal circle reactor core of Chinese press water stack nuclear power station |
| CN101572127A (en) * | 2008-04-28 | 2009-11-04 | 中科华核电技术研究院有限公司 | Nuclear fuel rod, nuclear fuel component and nuclear reactor core |
Non-Patent Citations (1)
| Title |
|---|
| 程和平 等: "百万级核电站长周期低泄漏堆芯燃料管理设计研究", 《中国核学会2001学术年会论文集》, 31 December 2001 (2001-12-31), pages 580 - 582 * |
Cited By (20)
| 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 |
| CN103680652A (en) * | 2013-12-03 | 2014-03-26 | 中国核电工程有限公司 | Reactor core loading method with first firing cycle adopting fuel assemblies having one enrichment degree |
| 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 |
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
| CN105280256A (en) * | 2014-05-29 | 2016-01-27 | 江苏核电有限公司 | Leading fuel assembly mixing reactor core loading method |
| CN104952492A (en) * | 2015-05-11 | 2015-09-30 | 中国核动力研究设计院 | Gadolinium-carrying fuel rod, fuel assembly with gadolinium-carrying fuel rods and pressurized water reactor core |
| 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 |
| CN105139900A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | 24-Month reload core loading method adopting erbium inflammable poison |
| 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 |
| CN107863166A (en) * | 2017-12-08 | 2018-03-30 | 中国核动力研究设计院 | A kind of stowage of reloading for 18 months of the first circulation boracic reactor core of presurized water reactor |
| CN107910078A (en) * | 2017-12-08 | 2018-04-13 | 中国核动力研究设计院 | 18 months of a kind of pressurized water reactor core are reloaded the management method of multi-cycle fuel |
| CN108039216A (en) * | 2017-12-08 | 2018-05-15 | 中国核动力研究设计院 | A kind of balanced recycle of pressurized water reactor core reloads stowage for 18 months |
| 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 |
| 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 |
| 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 |
| 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 |
| CN113496784A (en) * | 2020-04-03 | 2021-10-12 | 华龙国际核电技术有限公司 | Reactor core of nuclear power station reactor |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN103000232B (en) | 2015-07-29 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103000232B (en) | The head of a kind of advanced person circulates stowage of reloading for 18 months | |
| CN103578588A (en) | Reactor core loading method for exchanging fuels of pressurized water reactor nuclear power plant after 18 months of balanced circulation | |
| CN101241772B (en) | 18-month feed replacement method for 1-million kW unit of China PWR nuclear power station | |
| CN102332315B (en) | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant | |
| JPS61111488A (en) | Fuel load for core of nuclear reactor and operating method thereof | |
| CN101226782B (en) | Stowage method of million kilowatt units principal circle reactor core of Chinese press water stack nuclear power station | |
| CN108053904B (en) | A kind of 18 months stowages of reloading of presurized water reactor head circulation reactor core containing gadolinium | |
| Hibi et al. | Conceptual designing of reduced-moderation water reactor with heavy water coolant | |
| CN107863166A (en) | A kind of stowage of reloading for 18 months of the first circulation boracic reactor core of presurized water reactor | |
| CN107093479A (en) | A kind of first circulatory life-time length core loading method of 24 months of presurized water reactor | |
| CN104952492B (en) | Carry gadolinia fuel rod and with the fuel assembly and pressurized water reactor core for carrying gadolinia fuel rod | |
| US4587089A (en) | Fuel assembly for boiling water reactor | |
| CN103400619B (en) | The stowage of reloading in a kind of advanced person's 1/4 reactor core year | |
| CN103680652B (en) | First circulation uses the core loading method of the fuel assembly of a kind of enrichment | |
| CN107093478A (en) | A kind of pressurized water reactor core balanced recycle material-changing method of 24 months | |
| Boczar et al. | Reactor physics studies for a pressure tube supercritical water reactor (PT-SCWR) | |
| CN207441262U (en) | A kind of reactor core | |
| CN107910077B (en) | VVER reactor type length-alternating balance cycle reactor core loading method | |
| Kim et al. | Once-through thorium fuel cycle options for the advanced PWR core | |
| JP2004301831A (en) | Boiling water reactor light water reactor core and fuel assembly | |
| CN107910078A (en) | 18 months of a kind of pressurized water reactor core are reloaded the management method of multi-cycle fuel | |
| Bibilashvill et al. | VVER Fuel Performance and Economics: Status and Improvement Prospects | |
| Ponomarenko | Peculiarities of Neutronics Characteristics of Integral Reactor WWER of Small Capacity | |
| Ponomarenko | Innovation in Power Maneuvering Mode for NPP Hanhikivi with WWER-1200 reactor | |
| CN117038132A (en) | Core loading method for achieving 24-month circulation of VVER reactor type by using poison erbium |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |