CN102117664B - Double-row hexagonal fuel assembly for supercritical water-cooled reactor - Google Patents

Double-row hexagonal fuel assembly for supercritical water-cooled reactor Download PDF

Info

Publication number
CN102117664B
CN102117664B CN2010106052340A CN201010605234A CN102117664B CN 102117664 B CN102117664 B CN 102117664B CN 2010106052340 A CN2010106052340 A CN 2010106052340A CN 201010605234 A CN201010605234 A CN 201010605234A CN 102117664 B CN102117664 B CN 102117664B
Authority
CN
China
Prior art keywords
hexagon
assembly
moderator
passage
fuel
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.)
Active
Application number
CN2010106052340A
Other languages
Chinese (zh)
Other versions
CN102117664A (en
Inventor
王连杰
秦冬
李庆
于颖锐
夏榜样
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Power Institute of China
Original Assignee
Nuclear Power Institute of China
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN2010106052340A priority Critical patent/CN102117664B/en
Publication of CN102117664A publication Critical patent/CN102117664A/en
Application granted granted Critical
Publication of CN102117664B publication Critical patent/CN102117664B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • 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

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to the technical field of nuclear reactor fuel assemblies, particularly relates to a double-row hexagonal fuel assembly for a supercritical water-cooled reactor, and aims at providing a fuel assembly with better uniform and full moderation capability and a local power peak value as low as possible. A plurality of hexagonal moderator channels are arranged inside a hexagonal assembly box of the fuel assembly; two layers of fuel rods are arranged between the adjacent hexagonal moderator channels; a central hexagonal moderator channel which has the same structure with the hexagonal assembly box and is scaled down is arranged in the center of the hexagonal assembly box; continuously and repeatedly arrayed hexagonal moderator channels are arranged on each side of the central hexagonal moderator channels; and a plurality of trapezoid moderator channels are arranged on the edges of the assembly. In the double-row hexagonal fuel assembly provided by the invention, the two layers of fuel rods are arranged between the adjacent hexagonal moderator channels, thus the defect that the single row of fuel rods has weak moderation capability to the fuel rods close to the assembly box is overcome and the moderation effect of the fuel rods at angular points of the moderator channels is improved.

Description

Be applied to the double hexagon fuel assembly of Supercritical-Pressure Light Water Cooled Reactor
Technical field
The invention belongs to the fuel assembly for nuclear reactor technical field, be specifically related to a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor.
Background technology
Because the enthalpy that supercritical water is larger rises and lower power density, the design of Supercritical-Pressure Light Water Cooled Reactor (SCWR) assembly relates to strong physics thermal technology coupling.The neutron economy of assembly and structural complexity will directly affect the economy of SCWR reactor core, and the economy advantage of SCWR reactor core is mainly reflected in the high and simplified equipment of system thermal efficiency.In order to obtain higher coolant outlet temperature, and then improve system thermal efficiency, the power that need to flatten as far as possible in the assembly distributes, and reduces local power peaking's factor.In order effectively to reduce local power peaking's factor, multiple fuel assembly Conceptual Design was proposed once in the world.
At present, the fuel assembly type that is applied to Supercritical-Pressure Light Water Cooled Reactor that proposes in the world mainly is divided into hexagonal fuel assembly and square fuel assembly.The hexagonal fuel assembly scheme mainly contains the Dobashi assembly scheme (seeing Fig. 1) of Japanese Supercritical-Pressure Light Water Cooled Reactor SCLWR use and the scheme (seeing Fig. 2) that calendar year 2001 Bittermann proposes, and is single fuel rod arrangement mode.The square fuel assembly scheme mainly contains single square fuel assembly (seeing Fig. 3) and double square fuel assembly (seeing Fig. 4).
In the Dobashi of single hexagon fuel assembly scheme, the fuel rod of assembly center and peripheral distributes more intensive than inferior limit part, the suffered slowing down of the fuel rod of dense distribution is weaker than equally distributed fuel rod, in the situation of same fuel enrichment, such layout must make local power peaking's factor of whole assembly higher.In order to address this problem, having to has increased the complexity of assembly and Core Design at the fuel rod of three kinds of fuel enrichments of a component internal employing.
There is the inhomogeneous problem of slowing down equally in Bittermann assembly scheme, even the fuel rod of six corner points is changed into the stainless steel solid rod, and the factor F of local power peaking when assembly adopts 6% homogeneous enrichment fuel rod LAlso near 1.30.
For square assembly scheme, Fig. 3 has provided a kind of preferred arrangement mode of single square fuel assembly, has adopted the fuel rod of 2 kinds of enrichments in the assembly.Fig. 4 has provided the schematic diagram of double square fuel assembly, adopts the fuel rod of same enrichment in the assembly.The circumferential homogeneity of square water rod slowing down effect is relatively poor, and the suffered slowing down difference on effect of the fuel rod of diverse location is larger around the water rod.Although double square assembly has overcome single square assembly near the weak shortcoming of the fuel rod slowing down of assembly housing, the slowing down of the fuel rod of water rod corner point is improved and not obvious, obvious power distributional difference still can appear.
In " arrangement analysis of supercritical water reactor fuel assembly " that " Nuclear Science And Engineering " the 1st phase in 2009 delivers, several arrangement modes to the supercritical water reactor fuel assembly have carried out simple analysis, the hexagon assembly scheme of wherein mentioning, but research is comparatively preliminary in the literary composition, and there are a lot of problems in the assembly of proposition.At first, use zircoium hydride slowing material and stainless steel neutron absorber in the assembly, increased the complexity of modular construction design, reduced the neutron economy of assembly; Secondly, the assembly scheme of wherein mentioning adopts thin fuel rod, and size of components and fuel loading amount are less, is unfavorable for that control rod drive mechanisms (CRD) is arranged and reactor fuel loads layout; In addition, scheme is not considered structural behaviour and the thermal property of assembly in the literary composition, and the assembly housing wall thickness in the assembly, slowing down box ancient piece of jade, round, flat and with a hole in its centre thickness etc. does not possess the engineering realizability.Just to the simple contrast of various possible arrangement modes, do not form actual product and arrangement of components scheme in the literary composition.
Summary of the invention
The purpose of this invention is to provide a kind of have preferably evenly slowing down and abundant moderating power, the local power peaking's factor low double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor of trying one's best.
Technical scheme of the present invention is:
A kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: be equipped with a plurality of hexagon moderator passages in hexagon assembly box inside, between adjacent hexagon moderator passage, arrange two-layer fuel rod.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: be equipped with at described hexagon assembly box center one with hexagon assembly box isostructure, scaled center hexagon moderator passage, the hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, described assembly edge adopts a plurality of trapezoidal moderator passages.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: the empty water gap place in described trapezoidal slowing down passage both sides arranges hollow or solid keeper.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: structured material, guide pipe, involucrum and box wall material in the described fuel assembly all adopt Inconel718 or stainless steel 310S.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: described hexagon moderator passage is got 0.8~1.8mm, and the box wall thickness of trapezoidal moderator passage is got 0.8~1.8mm, and the assembly housing wall thickness is got 1~2mm.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: be equipped with at described hexagon assembly box center one with hexagon assembly box quadrature, scaled center hexagon moderator passage, the hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, described assembly edge adopts a plurality of triangle moderator passages.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: be equipped with at described hexagon assembly box center one with hexagon assembly box isostructure, scaled center hexagon moderator passage, the hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, described assembly edge adopt the moderator passage of a plurality of trapezoidal or rhombuses.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: the hexagon moderator port number in described hexagon assembly box is 13, each edge of described assembly is provided with a trapezoidal moderator passage.
Aforesaid a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, wherein: the hexagon moderator port number in described hexagon assembly box is nineteen, each edge of described assembly is provided with two trapezoidal moderator passages.
The invention has the beneficial effects as follows:
1. the present invention proposes the assembly concept of between adjacent hexagons moderator passage, arranging two-layer fuel rod, both overcome single fuel rod arrangement near the weak shortcoming of the fuel rod slowing down of assembly housing, effectively improved again the slowing down effect of moderator passage corner point fuel rod;
2. near the empty water gap place the trapezoidal slowing down passage has arranged the structured material keeper in assembly, keeper can squeeze away sky water gap place portion cooling agent on the one hand, reduction is near the moderating power of the fuel rod water gap, keeper absorption neutron ability is stronger on the other hand, so keeper can effectively suppress near the power density of the fuel rod of empty water gap, flatten the assembly internal power and distribute;
3. the present invention has improved the even slowing down of assembly and abundant moderating power by increasing trapezoidal grid or triangular lattice in hexagon assembly box wall inside edge;
4. consider the engineerings application correlative factors such as assembly centre distance, uranium loading amount in the fuel assembly design, proposed respectively to be applicable to four kinds of assembly schemes of thin fuel rod and thick fuel rod;
5. structural behaviour and the thermal property of the present invention by considering assembly chosen suitable hexagon moderator box wall thickness, assembly housing wall thickness and structured material;
6. by the layout in assembly for thin rod and thick rod, local power peaking's factor can be down to below 1.10.
Description of drawings
Fig. 1 is Dobashi assembly scheme schematic diagram in the prior art;
Fig. 2 is Bittermann assembly scheme schematic diagram in the prior art;
Fig. 3 is single square assembly scheme arrangement figure (1/4 assembly) in the prior art;
Fig. 4 is double square assembly scheme schematic diagram in the prior art;
Fig. 5 is a kind of the first embodiment schematic diagram that is applied to the double hexagon fuel assembly of Supercritical-Pressure Light Water Cooled Reactor provided by the invention;
Fig. 6 is a kind of double hexagon assembly of the second embodiment schematic diagram that is applied to the double hexagon fuel assembly of Supercritical-Pressure Light Water Cooled Reactor provided by the invention;
Fig. 7 is a kind of double hexagon assembly of the 3rd embodiment schematic diagram that is applied to the double hexagon fuel assembly of Supercritical-Pressure Light Water Cooled Reactor provided by the invention;
Fig. 8 is a kind of double hexagon assembly of the 4th embodiment schematic diagram that is applied to the double hexagon fuel assembly of Supercritical-Pressure Light Water Cooled Reactor provided by the invention;
Among the figure, 1 keeper; 2 assembly housings; 3 fuel rods; 4 trapezoidal moderator passages; 5 hexagon moderator passages; 6 center gauge pipes; 7 control rod guide pipes; 8. slowing down water is excellent.
Embodiment
Below in conjunction with accompanying drawing and embodiment a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor that the present invention proposes is further introduced:
Fuel rod 3 can be divided into thin rod and thick rod, and usually thin rod refers to that diameter D is less than the fuel rod of 9.5mm; Thick rod is often referred to diameter D more than or equal to the fuel rod of 9.5mm.
Embodiment 1:
As shown in Figure 5, a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, the a plurality of hexagon moderator passages 5 of its inner employing, the edge adopts a plurality of trapezoidal moderator passages 4, between adjacent hexagons moderator passage 5, arrange two-layer fuel rod 3, arrange keeper 1 at the empty water gap place of described trapezoidal slowing down passage 4 both sides; Structured material, guide pipe, involucrum and box wall material in the assembly all adopt Inconel718 or stainless steel 310S; Hexagon moderator passage 5 box walls and the desirable 0.8~1.8mm of trapezoidal moderator passage 4 box wall thickness, the assembly housing wall thickness is got 1~2mm; More excellent, hexagon moderator passage 5 box walls and trapezoidal moderator passage 4 box wall thickness are all got 0.8mm in the present embodiment, and the assembly housing wall thickness is got 1mm.
The diameter of described fuel rod 3 is D=10.2mm, and the P/D of assembly (pitch rod footpath than) is 1.3, and the hexagonal outer opposite side distance 238.8mm of hexagon fuel assembly xsect has 186 fuel rods in single case assembly, uranium dioxide loading amount 486kg.
The center of hexagon fuel assembly is provided with and assembly isostructure, scaled center hexagon moderator passage, and its opposite side distance is 32.42mm; The hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, adjacent hexagons moderator channel center distance is 59.2mm; Be provided with a trapezoidal moderator passage at the center on each limit of hexagon fuel assembly, this trapezoidal moderator passage is half of hexagon moderator passage.
Be positioned at gauge pipe 6 centered by the hexagon moderator passage 5 in the middle of the hexagon fuel assembly, in six moderator passages adjacent with center hexagon moderator passage 5 control rod guide pipe 7 can be set.
The assembly slowing down that this embodiment provides is comparatively even, not with the factor F of local power peaking of assembly under keeper 1 and control rod guide pipe 7 situations LBe 1.098.When adopting solid keeper 1, assembly has, the F during without the control rod guide pipe LBe respectively 1.049 and 1.048, all be lower than 1.10 desired value.The described factor F of local power peaking LFor: maximum fuel rod power density is divided by the average power density of assembly internal combustion charge bar.
Embodiment 2:
As shown in Figure 6, a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, the a plurality of hexagon moderator passages 5 of its inner employing, the edge adopts a plurality of trapezoidal moderator passages 4, arrange two-layer fuel rod 3 between adjacent hexagons moderator passage 5, near the empty water gap place described trapezoidal slowing down passage 4 arranges keeper 1; Structured material, guide pipe, involucrum and box wall material in the assembly all adopt Inconel718 or stainless steel 310S; Hexagon moderator passage 5 box walls and the desirable 0.8~1.8mm of trapezoidal moderator passage 4 box wall thickness, the assembly housing wall thickness is got 1~2mm; More excellent, hexagon moderator passage 5 box walls and trapezoidal moderator passage 4 box wall thickness are all got 0.8mm in the present embodiment, and the assembly housing wall thickness is got 1mm.
The diameter of described fuel rod 3 is D=8.0mm, and the P/D of assembly (pitch rod footpath than) is 1.3, and the hexagonal outer opposite side distance 234.1mm of hexagon fuel assembly xsect has 288 fuel rods in single case assembly, uranium dioxide loading amount 464kg.
The center of hexagon fuel assembly is provided with and assembly isostructure, scaled center hexagon moderator passage, and its opposite side distance is 25.63mm; The hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, adjacent hexagons moderator channel center distance is 46.42mm; Be provided with two trapezoidal moderator passages on each limit of hexagon fuel assembly, this trapezoidal moderator passage is half of hexagon moderator passage.
Be positioned at gauge pipe 6 centered by the hexagon moderator passage 5 in the middle of the hexagon fuel assembly, in center hexagon moderator passage 5 12 moderator passages on every side control rod guide pipe 7 can be set.
Embodiment 3:
As shown in Figure 7, a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, the a plurality of hexagon moderator passages 5 of its inner employing, the edge adopts a plurality of trapezoidal moderator passages 4, arrange two-layer fuel rod 3 between adjacent hexagons moderator passage 5, near the empty water gap place described trapezoidal slowing down passage 4 arranges keeper 1; Structured material, guide pipe, involucrum and box wall material in the assembly all adopt Inconel718 or stainless steel 310S; Hexagon moderator passage 5 box walls and the desirable 0.8~1.8mm of trapezoidal moderator passage 4 box wall thickness, the assembly housing wall thickness is got 1~2mm; More excellent, hexagon moderator passage 5 box walls and trapezoidal moderator passage 4 box wall thickness are all got 0.8mm in the present embodiment, and the assembly housing wall thickness is got 1mm.
The diameter of described fuel rod 3 is D=8.0mm, and the P/D of assembly (pitch rod footpath than) is 1.3, and the hexagonal outer opposite side distance 295mm of hexagon fuel assembly xsect has 444 fuel rods in single case assembly, uranium dioxide loading amount 715kg.
The center of hexagon fuel assembly is provided with and assembly quadrature, scaled center hexagon moderator passage, and its opposite side distance is 25.63mm; The hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, adjacent hexagons moderator channel center distance is 46.42mm; Be provided with a plurality of triangle moderator passages on each limit of hexagon fuel assembly.
Embodiment 4:
As shown in Figure 8, a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, the a plurality of hexagon moderator passages 5 of its inner employing, the edge adopts a plurality of trapezoidal moderator passages 4, arrange two-layer fuel rod 3 between adjacent hexagons moderator passage 5, near the empty water gap place described trapezoidal slowing down passage 4 arranges keeper 1; Structured material, guide pipe, involucrum and box wall material in the assembly all adopt Inconel718 or stainless steel 310S; Hexagon moderator passage 5 box walls and the desirable 0.8~1.8mm of trapezoidal moderator passage 4 box wall thickness, the assembly housing wall thickness is got 1~2mm; More excellent, hexagon moderator passage 5 box walls and trapezoidal moderator passage 4 box wall thickness are all got 0.8mm in the present embodiment, and the assembly housing wall thickness is got 1mm.
The diameter of described fuel rod 3 is D=8.0mm, and the P/D of assembly (pitch rod footpath than) is 1.3, and the hexagonal outer opposite side distance 279mm of hexagon fuel assembly xsect has 420 fuel rods in single case assembly, uranium dioxide loading amount 677kg.
The center of hexagon fuel assembly is provided with and assembly isostructure, scaled center hexagon moderator passage, and its opposite side distance is 25.63mm; The hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, adjacent hexagons moderator channel center distance is 46.42mm; Be provided with the moderator passage of a plurality of trapezoidal or rhombuses on each limit of hexagon fuel assembly.
The opposite side distance of embodiment 3 and embodiment 4 assemblies is larger, be conducive to control rod drive mechanisms (CRD) layout and reactor core and arrange, but kind and the number of special-shaped grid is more in the assembly, are unfavorable for the realization of modular construction.
Special-shaped grid kind and the number of embodiment 1 and embodiment 2 are less, are conducive to the realization of modular construction.
Table 1 has provided embodiment 1 under different guide pipes, keeper and the trapezoidal moderator box wall thickness and the physical property result of calculation of embodiment 2 assembly schemes.By as seen from Table 1, for not with embodiment 2 assemblies of keeper and guide pipe, there are 2 adjacent empty water gaps at 6 drift angle places of assembly, cooling medium is more, and comparatively abundant to the fuel rod slowing down near corner point, its power density is higher, causes the F of assembly LLarge (1.171).And the fuel rod slowing down of other positions is even in the assembly, and the power nonuniformity coefficient is lower than 1.05 substantially.
Power density near the fuel rod empty water gap of establishment flattens the assembly internal power and distributes, and can consider at the hollow or solid keeper of empty water gap place layout.Keeper has squeezed away empty water gap place portion cooling agent on the one hand, and keeper absorption neutron ability is stronger on the other hand, so keeper can effectively suppress near the power density of the fuel rod of empty water gap.Use same enrichment fuel if be not limited to, can consider to reduce near the enrichment of the fuel rod of empty water gap, but can not embody like this advantage that double hexagon assembly fuel rod type is simplified.
Calculating shows, empty water gap place adopts solid keeper can make F without control rod guide pipe assembly LBe down to 1.061, the F under the corresponding tape guide pipe assembly situation LBe 1.105.If want to make assembly have, without the F under the guide pipe situation LAll be lower than 1.10, then can increase the wall thickness of trapezoidal moderator box, if trapezoidal moderator box wall thickness increases to 1.8mm, assembly has, the F during without guide pipe LCan be down to respectively 1.043 and 1.051.
The double hexagon assembly of table 1 scheme physical property

Claims (7)

1. double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor, it is characterized in that: be equipped with a plurality of hexagon moderator passages (5) in hexagon assembly box (2) inside, between adjacent hexagon moderator passage (5), arrange two-layer fuel rod (3); Be equipped with at described hexagon assembly box (2) center one with hexagon assembly box (2) isostructure, scaled center hexagon moderator passage (5), the hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, described assembly edge adopts a plurality of trapezoidal moderator passages (4); Empty water gap place in described trapezoidal slowing down passage (4) both sides arranges hollow or solid keeper (1).
2. a double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor is equipped with a plurality of hexagon moderator passages (5) in hexagon assembly box (2) inside, arranges two-layer fuel rod (3) between adjacent hexagon moderator passage (5); It is characterized in that: be equipped with at described hexagon assembly box (2) center one with hexagon assembly box (2) quadrature, scaled center hexagon moderator passage (5), the hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, described assembly edge adopts a plurality of triangle moderator passages.
3. a double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor is equipped with a plurality of hexagon moderator passages (5) in hexagon assembly box (2) inside, arranges two-layer fuel rod (3) between adjacent hexagon moderator passage (5); It is characterized in that: be equipped with at described hexagon assembly box (2) center one with hexagon assembly box (2) isostructure, scaled center hexagon moderator passage (5), the hexagon moderator passage that each limit of described center hexagon moderator passage has continuous repeated arrangement, described assembly edge adopt the moderator passage of a plurality of trapezoidal and rhombuses.
4. such as the arbitrary described a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor of claim 1~3, it is characterized in that: structured material, guide pipe, involucrum and box wall material in the described fuel assembly all adopt Inconel718 or stainless steel 310S.
5. such as the arbitrary described a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor of claim 1~3, it is characterized in that: the box wall thickness of described hexagon moderator passage (5) is got 0.8~1.8mm, the box wall thickness of trapezoidal moderator passage (4) is got 0.8~1.8mm, and assembly housing (2) wall thickness is got 1~2mm.
6. a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor as claimed in claim 1, it is characterized in that: hexagon moderator passage (5) number in described hexagon assembly box (2) is 13, and each edge of described assembly is provided with a trapezoidal moderator passage (4).
7. a kind of double hexagon fuel assembly that is applied to Supercritical-Pressure Light Water Cooled Reactor as claimed in claim 1, it is characterized in that: hexagon moderator passage (5) number in described hexagon assembly box (2) is nineteen, and each edge of described assembly is provided with two trapezoidal moderator passages (4).
CN2010106052340A 2010-12-24 2010-12-24 Double-row hexagonal fuel assembly for supercritical water-cooled reactor Active CN102117664B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN2010106052340A CN102117664B (en) 2010-12-24 2010-12-24 Double-row hexagonal fuel assembly for supercritical water-cooled reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN2010106052340A CN102117664B (en) 2010-12-24 2010-12-24 Double-row hexagonal fuel assembly for supercritical water-cooled reactor

Publications (2)

Publication Number Publication Date
CN102117664A CN102117664A (en) 2011-07-06
CN102117664B true CN102117664B (en) 2013-01-02

Family

ID=44216380

Family Applications (1)

Application Number Title Priority Date Filing Date
CN2010106052340A Active CN102117664B (en) 2010-12-24 2010-12-24 Double-row hexagonal fuel assembly for supercritical water-cooled reactor

Country Status (1)

Country Link
CN (1) CN102117664B (en)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102354539A (en) * 2011-09-15 2012-02-15 西安交通大学 Annular fuel element and annular fuel supercritical water reactor
CN102592688B (en) * 2012-03-02 2014-10-08 华北电力大学 Double-layer water rod assembly structure for supercritical water cooled reactor
CN103137219B (en) * 2013-02-04 2015-10-28 中国核动力研究设计院 A kind of reactor layered fuel assembly
CN103151080B (en) * 2013-02-04 2015-07-15 中国核动力研究设计院 Self-tightening sealed structure for refueling water level control of reactor
CN103366837A (en) * 2013-07-23 2013-10-23 中国核动力研究设计院 Supercritical water cooled reactor fuel assembly and reactor core
CN106504800B (en) * 2016-11-25 2018-05-25 中国核动力研究设计院 A kind of Supercritical-Pressure Light Water Cooled Reactor control rod stowage and structure
CN109935354A (en) * 2017-12-19 2019-06-25 中国原子能科学研究院 A kind of two-sided cooling annular fuel assembly of hexagon
CN109243645B (en) * 2018-09-13 2022-03-01 中国核动力研究设计院 Spent fuel assembly storage grillwork
CN110111913B (en) * 2018-09-13 2022-02-11 中国核动力研究设计院 Test reactor core and method for measuring neutron fluence rate of hexagonal sleeve type fuel reactor core
CN110853772B (en) * 2019-11-21 2021-07-13 中国核动力研究设计院 Single-flow supercritical water-cooled reactor based on square fuel assembly
CN110853770B (en) * 2019-11-21 2021-07-20 中国核动力研究设计院 Single-flow supercritical water-cooled reactor based on regular hexagonal fuel assembly
CN110853773A (en) * 2019-11-21 2020-02-28 中国核动力研究设计院 Axial reverse-charging metal cooling reactor and management method
CN112420222B (en) * 2020-11-19 2022-02-11 中国核动力研究设计院 Control rod arrangement method for reactor core fuel assembly and control rod assembly
CN115394458B (en) * 2022-08-26 2024-08-20 中国核动力研究设计院 Ultra-high flux reactor core based on bar-bundle type fuel assembly
CN115600518B (en) * 2022-10-20 2023-11-10 中国核动力研究设计院 Fuel assembly thermal performance analysis method and system based on phase distribution characteristics

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2001004774A (en) * 1999-06-22 2001-01-12 Yoshiaki Oka Supercritical pressure light water cooled fast reactor
JP2003139881A (en) * 2001-10-30 2003-05-14 Toshiba Corp Reactor cooled with supercritical pressure water, channel box, water rod and fuel assembly
JP2003294878A (en) * 2002-04-03 2003-10-15 Yoshiaki Oka Fuel assembly
JP2005221491A (en) * 2004-02-03 2005-08-18 Yoshiaki Oka Supercritical water-cooled nuclear reactor
CN1700359A (en) * 2005-03-18 2005-11-23 张育曼 Supercritical water nuclear reactor utilizing sleeve fuel assembly
JP4559957B2 (en) * 2005-11-18 2010-10-13 株式会社東芝 Reactor with fuel assembly and core loaded with this fuel assembly

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2001004774A (en) * 1999-06-22 2001-01-12 Yoshiaki Oka Supercritical pressure light water cooled fast reactor
JP2003139881A (en) * 2001-10-30 2003-05-14 Toshiba Corp Reactor cooled with supercritical pressure water, channel box, water rod and fuel assembly
JP2003294878A (en) * 2002-04-03 2003-10-15 Yoshiaki Oka Fuel assembly
JP2005221491A (en) * 2004-02-03 2005-08-18 Yoshiaki Oka Supercritical water-cooled nuclear reactor
CN1700359A (en) * 2005-03-18 2005-11-23 张育曼 Supercritical water nuclear reactor utilizing sleeve fuel assembly
JP4559957B2 (en) * 2005-11-18 2010-10-13 株式会社東芝 Reactor with fuel assembly and core loaded with this fuel assembly

Non-Patent Citations (5)

* Cited by examiner, † Cited by third party
Title
J. Hofmeister, et.al..Fuel assembly design study for a reactor with supercritical water.《Nuclear Energy and Design》.2007,第237卷(第14期),1513-1521. *
X.J. Liu, X. Cheng.Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly.《Annals of Nuclear Energy》.2008,第36卷(第1期),28-36. *
常华健.超临界水堆燃料组件内的排列研究.《核科学与工程》.2009,第29卷(第1期), *
王连杰等.SCWR双排六边形燃料组件物理性能分析.《核动力工程》.2010,第31卷(第S2期), *
秦冬 *

Also Published As

Publication number Publication date
CN102117664A (en) 2011-07-06

Similar Documents

Publication Publication Date Title
CN102117664B (en) Double-row hexagonal fuel assembly for supercritical water-cooled reactor
CN108648834B (en) Honeycomb briquet type fuel assembly and the cooling fast reactor reactor core of small size long-life lead bismuth
CN103390434B (en) A kind of novel fine rod tight lattice nuclear reactor
CN110853774B (en) Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor
CN103578578B (en) A kind of fusion-fission subcritical energy source reactor core fuel assembly of advanced person
CN103474101A (en) Nuclear reactor core arrangement of nuclear power station
CN104183279A (en) Inner-cooling pressurized-water reactor core
CN113674877A (en) Lead-based fast reactor magnesium oxide reflecting layer assembly and lead-bismuth fast spectrum reactor core arrangement
CN113674876A (en) Reactor core arrangement and component arrangement of metal-cooled reactor containing solid moderator
CN204288819U (en) A kind of inner-cooled pressurized-water reactor core
US20020136346A1 (en) Fuel element and gas coolant nuclear reactor using same
CN102592688A (en) Double-layer water rod assembly structure for supercritical water cooled reactor
JP5552458B2 (en) Exposure enhancement zone for nuclear bundles in boiling water reactors
US20030103594A1 (en) Monobloc fuel element and boiling water and fast spectrum nuclear reactor using such elements
CN206697238U (en) A kind of New-type fuel component suitable for Proliferation burner reactor
CN115101222B (en) Reactor core structure based on graphite-based dispersion micro-encapsulated fuel
CN202694816U (en) MOX (mixed oxide) fuel assembly structure applied to super-critical water reactor
CN113793702B (en) Intrinsic safety integrated small-sized villaumite cooling high-temperature reactor core
US8831165B2 (en) Fuel assembly
US20240312644A1 (en) Solid lithium-lead blanket for fusion reactor
CN102768863A (en) MOX (Mixed Oxide) fuel assembly structure suitable for supercritical water reactor
JPH0631744B2 (en) Boiling water reactor
Jin et al. Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor
GB2627100A (en) Plate-type fuel assembly and reactor core
Oh et al. Feasibility Study of Double-cooled Annular Fuel with KSNP (II)

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