CN204288819U - A kind of inner-cooled pressurized-water reactor core - Google Patents
A kind of inner-cooled pressurized-water reactor core Download PDFInfo
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- CN204288819U CN204288819U CN201420483005.XU CN201420483005U CN204288819U CN 204288819 U CN204288819 U CN 204288819U CN 201420483005 U CN201420483005 U CN 201420483005U CN 204288819 U CN204288819 U CN 204288819U
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- 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
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Abstract
The utility model discloses a kind of inner-cooled pressurized-water reactor core, comprise and form approximate circle cylinder by some box hexagonal fuel assemblies, every three hexagonal fuel assemblies form Y type surface of contact, Y shape tabular control rod is furnished with between several Y type surface of contact, pad between surface of contact between hexagonal fuel assembly is separated out water gap, hexagonal fuel assembly appearance forms outer envelope by zirconium-niobium alloy, each hexagonal fuel assembly is made up of several inner-cooled sexangle lattice cells, without cladding materials between sexangle lattice cell, sexangle lattice cell is by the circular coolant flow passages of centering and fuel mix, coolant flow passages is the runner that interior involucrum is formed, interior cladding materials is zirconium-niobium alloy, rose metal is filled between interior involucrum and fuel.Adopt integral type inner-cooled fuel assembly, unbraced structure, core coolant flow road is simple.Under larger coolant flow speed, it is little that the pressure drop of reactor core form drag and stream cause vibrations, can obtain higher output power.
Description
Technical field
The utility model belongs to nuclear reactor technology field, relates to a kind of inner-cooled pressurized-water reactor core.
Background technology
Under the prerequisite meeting safety limit, the output power improving reactor contributes to the economy and the miniaturization that promote nuclear reactor.The principal element of limited reactions heap output power is fuel can and fuel pellet central temperature.Can realize meeting the object promoting heap die output power under safety limit prerequisite by increase coolant flow, increase heat transfer area, reduction fuel element size.In reduction fuel element size, consider the feasibility of machining, minimum fuel rod diameter feasible is at present about 6.5mm; In increase heat transfer area, adopt the two cold fuel element of annular, reduce fuel element temperature, under the premise that security is guaranteed, core power can be promoted.
In the research of current pressurized water reactor hoisting power density, the design of minor diameter fuel element and annular fuel element all can reduce the centerline temperature of fuel pellet, but reduction fuel element diameter can cause the reduction of its physical strength and stream to cause the increase of chatter; The coolant flow passages of annular fuel element is complicated, is unfavorable for that reactor core designs, and cooling medium pressure drop simultaneously also will increase, and needs more powerful main pump to maintain primary Ioops forced circulation.
Pressurized water reactor fuel element is generally cluster structure, the coolant flow (flow velocity) of reactor core is determined jointly by thermal technology and waterpower (stream causes chatter), coolant flow increases, cause chatter by causing the stream of fuel element to increase, the friction of fuel can and grid spacer increases, and can have an impact to the integrity of fuel can.Therefore, the research at present by increasing coolant flow lifting pressurized water reactor power density is relatively less.In " the inner-cooled pressurized-water reactor core assembly neutronics Primary Study " of " reversion reactor core assembly neutronics problem Primary Study " that " University Of Nanhua's journal-natural science edition " the 26th volume the 3rd phase in 2012 delivers, " reversion pressurized water reactor hot-working hydraulic characteristic Primary Study " and " Nuclear Power Engineering " 201 years the 5th phase the 34th curly hair tables, neutronics and subchannel thermal hydraulic analysis are carried out to the fuel assembly of inner-cooled pressurized water reactor, do not formed actual product and Core Design scheme.
Utility model content
The purpose of this utility model is to provide a kind of inner-cooled pressurized-water reactor core, solve current pressurized water reactor, the design of minor diameter fuel element and annular fuel element all can reduce the centerline temperature of fuel pellet, but reduction fuel element diameter can cause the reduction of its physical strength and stream to cause the problem of the increase of chatter.
The technical scheme that the utility model adopts comprises forming approximate circle cylinder by some box hexagonal fuel assemblies, every three hexagonal fuel assemblies form Y type surface of contact, Y shape tabular control rod is furnished with between several Y type surface of contact, pad between surface of contact between hexagonal fuel assembly is separated out water gap, hexagonal fuel assembly appearance forms outer envelope by zirconium-niobium alloy, each hexagonal fuel assembly is made up of several inner-cooled sexangle lattice cells, without cladding materials between sexangle lattice cell, sexangle lattice cell is by the circular coolant flow passages of centering and fuel mix, coolant flow passages is the runner that interior involucrum is formed, interior cladding materials is zirconium-niobium alloy, rose metal is filled between interior involucrum and fuel.
Further, described hexagonal fuel assembly number is 187 boxes; Described hexagonal fuel assembly is rectangular cylinder; Described hexagonal fuel assembly opposite side distance is 213mm.
Further, the outer envelope thickness of described hexagonal fuel assembly is 9.8mm, and length is 3680mm.
Further, described sexangle lattice cell is 169.
Further, in described fuel, uranium enrichment is 10% ~ 13%.
Further, described coolant flow passages diameter is 11mm, and coolant flow passages is outward interior involucrum, and interior shell thickness is 0.68mm, and interior involucrum and fuel gap are 0.34mm.
Further, Y shape tabular control rod thickness is 7mm, and adopt B4C as neutron absorber, length 3680mm, thickness is 5mm.
Further, described fuel material is UTh
0.5zr
2.25h
5.625.
Adopt integral type inner-cooled fuel assembly, unbraced structure, core coolant flow road is simple.Under larger coolant flow speed, it is little that the pressure drop of reactor core form drag and stream cause vibrations, can obtain higher output power.
Accompanying drawing explanation
Fig. 1 is the utility model inner-cooled pressurized water reactor hexagonal fuel assembly inner structure schematic diagram;
Fig. 2 is the utility model inner-cooled pressurized-water reactor core arrangenent diagram;
Fig. 3 is the utility model inner-cooled pressurised water reactor fuel assemblies sexangle lattice cell structural drawing;
Fig. 4 is the utility model inner-cooled pressurised water reactor fuel assemblies and Y shape tabular control element schematic diagram;
Fig. 5 is the utility model reactor core effective multiplication factor schematic diagram over time;
Fig. 6 is the utility model reactor core average channel coolant outlet temperature cloud charts;
Fig. 7 is that the utility model reactor core average channel cooling medium goes out density degree cloud charts;
Fig. 8 is the variation diagram of the utility model reactor core average channel cooling medium pressure drop axial height;
Fig. 9 is the utility model reactor core hottest channel coolant outlet temperature cloud charts.
In figure, 1. hexagonal fuel assembly, 2.Y shape tabular control rod, 3. outer envelope, 4. sexangle lattice cell, 5. coolant flow passages, 6. fuel, involucrum 7..
Embodiment
Below in conjunction with the drawings and specific embodiments, the utility model is described in detail.
A kind of embodiment of the present utility model as depicted in figs. 1 and 2, forms approximate circle cylinder by hexagonal fuel assembly 1, active region height 3680mm, equivalent diameter 3660mm, heap core power 4000MW; As shown in Figure 3, hexagonal fuel assembly 1 is made up of inner-cooled sexangle lattice cell 4, without cladding materials between sexangle lattice cell 4, sexangle lattice cell 4 opposite side distance is 16.04mm, and hexagonal fuel assembly 1 is integral type " honeycomb briquette " shape structure, and hexagonal fuel assembly 1 opposite side distance is 213mm, in fuel 6, uranium enrichment is 10% ~ 13% adjustable, meet the core life of different length, the outer envelope 3 of hexagonal fuel assembly 1 is zirconium-niobium alloy, and thickness is 9.8mm.Fuel 6 adopts uranium thorium hydrogen zirconium thing fuel, and wherein the atomic ratio of U, Th, Zr, H is 1:0.5:2.25:5.625; Hexagonal fuel assembly 1 is " honeycomb briquette " shape inner-cooled, namely coolant flow passages 5 is positioned at every root hexagonal fuel assembly 1 center, coolant flow passages 5 diameter is 11mm, coolant flow passages 5 is outer is interior involucrum 7, and thickness is 0.68mm, and material is zirconium-niobium alloy, interior involucrum 7 is 0.34mm with fuel 6 gap, interior filling rose metal, accidental conditions, this alloy is liquid.Each assembly contains 169 inner-cooled coolant flow passages 5.
As shown in Figure 4, the whole inner-cooled pressurized-water reactor core of the utility model is preferably made up of 187 box hexagonal fuel assemblies 1, leaves water gap between hexagonal fuel assembly 1, and thickness is 12.24mm; Water gap between hexagonal fuel assembly 1 is for arranging Y shape tabular control rod 2, and Y shape tabular control rod 2 thickness is 7mm, and adopt B4C as neutron absorber, the preferred 3680mm of length, thickness is 5mm, and Y shape tabular control rod 2 is wrapped up by stainless steel, thickness 1mm.The total quantity visual response control overflow of Y shape tabular control rod 2 is determined, under " card rod " criterion, can realize the minimum shut down depth requirement of-1% Δ k/k.
Y shape tabular control rod 2 is totally two large class, i.e. regulating rod group and shut-down rod groups.By the enrichment of uranium, control rod quantity and arrangement in adjustment fuel, inner-cooled pressurized water reactor can be made to realize power and to control and the minimum shut down depth requirement under " blocking rod " criterion.Burnup reactivity shimming and traditional cluster structure pressurized water reactor of inner-cooled pressurized water reactor are similar, adopt chemical shimming mode (boric acid); Load Regulation and shutdown fast adopts control rod to realize.
This routine inner-cooled pressurized water reactor decision design parameter is as shown in table 1.
Table 1
| Parameter name | Value |
| Fuel type | UTh 0.5Zr 2.25H 5.625 |
| Active region height/mm | 3680 |
| Equivalent diameter/mm | 3660 |
| Fuel assembly opposite side distance/mm | 213 |
| Coolant flow passages quantity in fuel assembly/ | 169 |
| Coolant flow passages diameter/mm | 11 |
| Hexagon fuel lattice cell opposite side distance/mm | 16.04 |
| Interior shell thickness/mm | 0.68 |
| Fuel assembly outer envelope thickness/mm | 9.8 |
| Cladding materials | Zirconium-niobium alloy |
| Reactor fuel component count/box | 187 |
| Heap core power/MW | 4000 |
| Pressure vessel operating pressure/Mpa | 15.5 |
| Reactor core temperature in/DEG C | 295 |
| Core exit medial temperature/DEG C | 329.1 |
| Steady state condition peak cladding temperature/DEG C | 343.8 |
| Steady state condition Central Fuel line maximum temperature/DEG C | 438.1 |
| Enthalpy liter/(kJ/kg) | 195.2 |
| Reactor core effective discharge/(kg/s) | 20891 |
| Cooling medium mean flow rate/(m/s) | 9.44 |
| Core power density/(MW/m 3) | 119 |
| Fuel rating/(kw/kg Fuel) | 73.60 |
| Mean linear power density density/(W/cm) | 391 |
| Steady state condition peak line power density/(W/cm) | 880 |
| Unit rate of flow/[kg/ (Ws)] | 5.12×10 -6 |
| The minimum departure from nucleate boiling ratio of steady state condition | 1.79 |
| Reactor core pressure drop/Mpa | 0.138 |
According to above design parameter, as shown in Figure 5, the utility model, without the reactor core effective multiplication factor in any control element situation over time, for the uranium enrichment of 13%, can meet 18 months and reload requirement.The average channel of reactor core shown in Fig. 6 coolant outlet temperature cloud charts, the average channel of reactor core shown in Fig. 7 cooling medium goes out density degree cloud charts.Reactor has good circumferential homogeneity.The change of the average channel of reactor core shown in Fig. 8 cooling medium pressure drop axial height, inlet pressure is 15.5MPa, and reactor core pressure drop is less, is 0.138MPa.The hottest channel of reactor core shown in Fig. 9 coolant outlet temperature cloud charts, reactor core hottest channel outlet medial temperature is 616.42K (343.42 DEG C), is less than the saturation temperature 617.94K (344.79 DEG C) of reactor core operating pressure (15.5MPa).
Advantage of the present utility model has:
(1) pressurized-water reactor core of sexangle inner-cooled fuel assembly 1 is adopted, compared with traditional cluster structure pressurized water reactor, fuel 6 is contrary with the geometric arrangement mode of coolant flow passages 5, existing pressurized water reactor is cluster structure, fuel rod is outward cooling medium, and inner-cooled reactor core, cooling medium at center, outside outer fuel; Inner-cooled assembly does not need bracing structure (grid spacer), the fuel rod of existing presurized water reactor is elongated bar-shaped, length is about 360cm, and diameter is about 1cm, and a fuel assembly is made up of 264 clusters, for ensureing to be parallel to each other, need, axially installing locating device additional, namely to locate shelf, also play the effect of cross-brace, coolant flow passages 5 xsect is circular, and runner circumference homogeneity is better.
(2) adopt uranium thorium hydrogen zirconium thing as fuel, reactor core has from slowing down characteristic, makes inner-cooled pressurized water reactor have higher core power density.
(3) adopt inner-cooled fuel assembly, coolant flow passages 5 is not axially changing, and when reactor core flow velocity is higher, the pressure drop of reactor core form drag is little, and mixed without laterally handing over without Core cooling agent.And due to existing PWR fuel assembly be cluster structure, cooling medium is when (axis) flows through fuel rod from bottom to top, runner is open, therefore certain exist horizontal mixing, radial forces is applied to fuel rod, cause vibrations, and then cause fuel can to produce rub with location shelf, affect reactor safety.The utility model is under large flow condition, and it is minimum that reactor core stream causes chatter.
(4) inner-cooled fuel assembly is integral type " honeycomb briquette " structure.
(5) Control Component adopts " Y shape " platy structure.
(6) fuel can adopts and inhales the extremely low zirconium-niobium alloy of hydrogen rate, and fills tin-lead-bismuth liquid metal between fuel and interior involucrum, effectively can reduce the risk of the suction hydrogen embrittlement of fuel can.
Compared with piling with traditional cluster structural response, the utility model adopts sexangle inner-cooled core structure, coolant flow passages 5 structure is simple, the even property of circumferential asymmetry is little, component internal does not need bracing structure, the form drag pressure drop of reactor core is low, and when adopting higher coolant flow speed, it is minimum that the stream of reactor core causes chatter; Fuel has from slowing properties, and the power density that reactor core allows is higher; Between hexagonal fuel assembly 1, adopt Y shape tabular control rod 2, control element on assembly inner flow passage without any impact; Adopt zirconium-niobium alloy involucrum, involucrum and fuel gap-fill tin-lead-bismuth liquid alloy, significantly can strengthen the heat transfer property of fuel and cooling medium, reduces involucrum simultaneously and inhale hydrogen embrittlement risk.The core structure of the utility model inner-cooled pressurized water reactor is more simple, and power density is higher, and it is minimum that stream causes chatter, also can be used for Marine Nuclear Power Plant except can be used for continental rise nuclear power plant.
The above is only to better embodiment of the present utility model, not any pro forma restriction is done to the utility model, every any simple modification above embodiment done according to technical spirit of the present utility model, equivalent variations and modification, all belong in the scope of technical solutions of the utility model.
Claims (8)
1. an inner-cooled pressurized-water reactor core, it is characterized in that: comprise and form approximate circle cylinder by some box hexagonal fuel assemblies (1), every three hexagonal fuel assemblies (1) form Y type surface of contact, Y shape tabular control rod (2) is furnished with between several Y type surface of contact, pad between surface of contact between hexagonal fuel assembly (1) is separated out water gap, hexagonal fuel assembly (1) appearance forms outer envelope (3) by zirconium-niobium alloy, each hexagonal fuel assembly (1) is made up of several inner-cooled sexangle lattice cells (4), without cladding materials between sexangle lattice cell (4), sexangle lattice cell (4) is made up of the circular coolant flow passages (5) of centering and fuel (6), the runner that coolant flow passages (5) is formed for interior involucrum (7), interior involucrum (7) material is zirconium-niobium alloy, rose metal is filled between interior involucrum (7) and fuel (6).
2. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: described hexagonal fuel assembly (1) number is 187 boxes; Described hexagonal fuel assembly (1) is rectangular cylinder; Described hexagonal fuel assembly (1) opposite side distance is 213mm.
3. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: outer envelope (3) thickness of described hexagonal fuel assembly (1) is 9.8mm, and length is 3680mm.
4. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: described sexangle lattice cell (4) is 169.
5. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: in described fuel (6), uranium enrichment is 10% ~ 13%.
6. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: described coolant flow passages (5) diameter is 11mm, coolant flow passages (5) is outward interior involucrum (7), interior involucrum (7) thickness is 0.68mm, and interior involucrum (7) and fuel (6) gap are 0.34mm.
7. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: Y shape tabular control rod (2) thickness is 7mm, adopt B4C as neutron absorber, length 3680mm, thickness is 5mm.
8. according to inner-cooled pressurized-water reactor core a kind of described in claim 1, it is characterized in that: described fuel (6) material is UTh
0.5zr
2.25h
5.625.
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|---|---|---|---|
| CN201420483005.XU CN204288819U (en) | 2014-08-26 | 2014-08-26 | A kind of inner-cooled pressurized-water reactor core |
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| CN201420483005.XU CN204288819U (en) | 2014-08-26 | 2014-08-26 | A kind of inner-cooled pressurized-water reactor core |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104183279A (en) * | 2014-08-26 | 2014-12-03 | 南华大学 | Inner-cooling pressurized-water reactor core |
| CN111781235A (en) * | 2020-07-07 | 2020-10-16 | 西安交通大学 | Experimental device and method for simulating thermal influence of fuel surface sediments on reactor core |
-
2014
- 2014-08-26 CN CN201420483005.XU patent/CN204288819U/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104183279A (en) * | 2014-08-26 | 2014-12-03 | 南华大学 | Inner-cooling pressurized-water reactor core |
| CN111781235A (en) * | 2020-07-07 | 2020-10-16 | 西安交通大学 | Experimental device and method for simulating thermal influence of fuel surface sediments on reactor core |
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| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20150422 Termination date: 20160826 |
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| CF01 | Termination of patent right due to non-payment of annual fee |