CN108648834A - Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core - Google Patents
Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core Download PDFInfo
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- CN108648834A CN108648834A CN201810354479.7A CN201810354479A CN108648834A CN 108648834 A CN108648834 A CN 108648834A CN 201810354479 A CN201810354479 A CN 201810354479A CN 108648834 A CN108648834 A CN 108648834A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/042—Fuel elements comprising casings with a mass of granular fuel with coolant passages through them
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
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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
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core, Core Design power 20MW, and 20 years phases in longevity, it can be achieved that on-board running, powered as military or civilian from far-off regions;The honeycomb briquet type fuel assembly is made of coolant channel pipe, channel pipe outer wall lead bismuth coating, fuel region, upper and lower reflecting layer, fuel upper cavity, upper low head up and down;Three kinds of different honeycomb type fuel assemblies of shared coolant channel radius;Reflection layer assembly, shielding layer assembly are all made of honeycomb-type structural;Control assembly and security component are controlled using innovative liquid absorption material;Based on the calculating research to reactor core parameter, optimize reactor core, and evaluation analysis is carried out to reactor core neutronics and thermal-hydraulic;18 years Operation at full power of design object reactor core, stressor 0.9, reactor core volume weight meet vehicle-mounted transport limitation, meet reactor core Thermal Design limit value and security requirement in core life operational process.
Description
Technical field
The invention belongs to nuclear reactor field of engineering technology, and in particular to honeycomb briquet type fuel assembly and use honeycomb briquet type
The small size long-life lead bismuth of fuel assembly cools down fast reactor reactor core.
Background technology
According to the world market evaluation studies that national nuclear tests room (NNL) carries out, small modular reactor (SMRs) tool
There is very big market potential, if economic benefits, by 2035, the market competition size estim ate of small modular heap was about
For 65-85GWe.The characteristics of SMR includes lower investment construction cost, is suitble to small grids, and reducing infrastructure and employee needs
It asks, capacity and non-electricity application can be increased as needed (drinking water produces, district heating or hydrogen manufacturing etc.).It is international in recent years
On proposed to be based on pressurized water reactor (PWR), boiling water reactor (BWR), liquid metal cooled fast heap (LMFR), air cooling is fast
The various SMR design concepts technologies of heap (GFR) and fusedsalt reactor.Liquid metal cooled fast heap (LMFR) is compared to other concepts
Technology is because the expansion reaction that operation and fuel and core internals are born under coolant normal pressure feeds back and has stronger safety
Property and economy.Multiple liquid metal cooled fast heap reactor core concepts, including Toshiba Corp and center electricity are proposed in the world
The design power of power industrial research institute joint development is 30MW, 4S (Super-Safe, the Small and that the phase in longevity is 30 years
Simple) sodium-cooled fast reactor;Some row STAR (Secure Transportable Autonomous Reactor) that the U.S. proposes
Modularization fast neutron reactor, 2011, Argonne National Laboratory (ANL) exploitation improved the 300MWth STAR of entitled SUPERSTAR
The cooling pool small modular fast reactor of lead.SUPERSTAR uses 15 years long core lifes, primary coolant system to use
100% Natural Circulation and S-CO2 Brayton cycle power converters;Russian physics is based on nuclear submarine with power engineering research institute
The development technique of reactor proposes SVBR-100 Core Design concepts.SVBR-100 is the small of the lead bismuth cooling of a 280MWth
Type Modules Fast Reactor, operation 8 years of not reloading.A variety of reactor core concepts that comparative analysis proposes can be seen that SMRs is designed as growing mostly
Service life reactor core runs in the phase in longevity and does not reload, lead/lead bismuth because of inert chemi-cal character, strong heat conductivity, have natural-circulation capacity etc.
Feature, by the coolant as main SMRs.
Invention content
The present invention provides honeycomb briquet type fuel assemblies and small size long-life lead bismuth to cool down fast reactor reactor core, reactor core hot merit
Rate 20MW, do not reload continuously Operation at full power 18 years, vehicle-mounted can become one can remote accessible transport moving electric power
Production equipment, purposes are the power supply of population 10000 or so from far-off regions or military specific weapon continued power etc..The reactor core has
Have the characteristics that reactor core it is small, it is light-weight, vehicle-mounted, long-life, safe can be achieved.
To achieve the goals above, present invention employs following technical schemes:
A kind of honeycomb briquet type fuel assembly, the fuel assembly include three kinds of components that structure is identical but diameter is different,
Section is hexagonal;Structure includes component walls 1, evenly arranged coolant channel 2 in an axial direction in component walls 1, in component walls 1,
Region outside coolant channel includes in an axial direction:The fuel region 3 at middle part, the fuel top air cavity 4 on 3 top of fuel region, on fuel
The upper reflecting layer 5-1 on 4 top of portion's air cavity, the lower reflecting layer 5-2 of 3 lower part of fuel region, the upper cover 6-1 on the tops upper reflecting layer 5-1,
The low head 6-2 of the lower reflecting layer lower parts 5-2.
The coolant channel of fuel region is cooled down by fuel region coolant channel 7, fuel region coolant channel wall 8 and fuel region
LBE coverings 9 between agent channel wall and fuel region form, and fuel region coolant channel is up and down.
The quantity of the coolant channel 2 is 37.
3 material of the fuel region use degree of enrichment for 19.75% UO2;Filled with helium in fuel top air cavity 4;
The upper reflecting layer 5-1 and lower reflecting layer 5-2 materials are MgO;The upper cover 6-1 and low head 6-2 materials are that T91 is stainless
Steel.
A kind of small size long-life lead bismuth cools down fast reactor reactor core, reactor core display fuel area fuel assembly 10, intermediate
Fuel region fuel assembly 11, outer fuel area fuel assembly 12, control assembly 13, security component 14, reflection layer assembly 15 and screen
Cover layer assembly 16;It is characterized in that, fuel area fuel assembly 10, intermediate fuel area fuel assembly 11 and the combustion of outer fuel area
Expect that component 12 uses the honeycomb briquet type fuel assembly, three kinds of fuel assemblies that structure is identical but diameter is different, fuel
Fuel assembly 10 coolant channel in area's is maximum, fuel assembly 11 coolant channel in intermediate fuel area takes second place, outer fuel area fuel stack
12 coolant channel of part is minimum, and subregion arrangement can flatten the component power of reactor core;All kinds of groups of the reactor core triangular arrangement
Part, most intermediate 1st circle of reactor core arrange 7 fuel area fuel assemblies 10 altogether with the 2nd circle;Uniform 6 centres of alternate arrangement of 3rd circle
Fuel region fuel assembly 11 and 6 control assemblies 13;4th circle 18 intermediate fuel area fuel assemblies 11 of arrangement;5th circle hexagon
Six angles position in, 3 control assemblies 13 of alternate arrangement and 3 security components 14, control assembly 13 and security component 14
Position is distributed in two equilateral triangles;5th circle removes six Angle Positions, remaining arranges outer fuel area fuel assembly 12;6th circle six
A Angle Position arranges 6 reflection layer assemblies 15, remaining arrangement outer fuel area fuel assembly 12;7th circle 36 reflecting layer groups of arrangement
Part 15;8th six Angle Position arranging shielding layer assemblies 16 of circle, remaining location arrangements reflect layer assembly 15;9th six Angle Positions of circle
Do not arrange component, 42 shielding layer assemblies 16 are arranged in remaining position altogether.
The shielding layer assembly 16 is identical as reflection 15 structure of layer assembly, and section is hexagonal;Structure include shielded layer or
Reflecting layer component walls 17, shielded layer or reflecting layer coolant channel 18, coolant channel fill reflecting layer 19 outside;Axial includes anti-
Penetrate layer 19 and the upper low head 20 positioned at 19 top and the bottom of reflecting layer.
The control assembly 13 be liquid control assembly, structure include control assembly wall 21, stagnant area 22, fill area 23,
Hexagon annulated column piston 24, indentation/suction sealing-plug 25, T91 coverings 26, echo area 27, cavity 28, control assembly coolant are logical
Road 29 and cylindrical channel 30;Control assembly wall 21 is regular hexagon structure, is wrapped on the outside of component;Coolant channel 29 is upper
The hexagon annulated column of lower perforation;Cavity 28 is located at component central upper portion position, is hexagonal prisms structure, is closed by T91 coverings 26;It is stagnant
It stays area 22 to be located at component upper outside position, is in hexagon annulated column shape between coolant channel 29 and component walls 21;Filling
Area 23 is located at component lower outside, is hexagon annulated column structure, between component walls 21 and echo area 27, the setting of intermediate position by
Fill area 23 transits to the Ring-cylindrical channel of empty cavity position, axial highly consistent with active region;Fill remaining component in echo area 27
Space;Indentation/suction sealing-plug 25 of hexagon annulated column is arranged at 22 top of stagnant area;Stagnant area 22 has six with 23 contact surface of fill area
Angular annulated column piston 24, isolation Li6 and Li7 materials;Stagnant area 22 is led to fill area 23 by 12 liquid absorption material cylinders
The perforation connection of road 30, cylindrical channel 30 are arranged in below module activity area height.
The liquid absorption material of the control assembly 13 uses the Li6 materials with larger fast neutron absorption cross-section;It is described
23 liquid filling material of fill area uses Li7 materials;Security component 14 and 13 structure having the same of control assembly.
There are coolant gaps, the coolant to use LBE materials, reactor core between the various assemblies that the heap in-core is placed
Normal pressure is run, and outlet temperature is 500 DEG C.
The equivalent core diameter is 100.24cm, core height 150cm.
Compared to the prior art the present invention, has the following advantages that:
1, the present invention uses honeycomb briquet type fuel assembly, coolant channel up and down, to design end socket up and down, fuel, anti-
Penetrate layer, air cavity is completely enclosed, compared with traditional components, cancel previous fuel rod club shaped structure, exchanged coolant and fuel
Position, formed a compact-sized complete fuel assembly.This honeycomb briquet type fuel assembly increases component volume of fuel and accounts for
Than reducing reactor core lead bismuth and cooling down agent content, effectively reduce heap core volume and reactor core weight.
2, when fuel is radially expanded, it is higher than when reactor core operation design LBE coverings between fuel on the outside of coolant channel
The LBE of fusing point can be extruded in the cavity referred to above fuel, can effectively solve fuel and be radially expanded to squeeze coolant channel pipe
Pressure problem and optimization coolant take away the ability of fuel region heat.
3, cavity above fuel is set, the fission gas due to fission generation is collected and handle the sky of fuel axial expansion
Between extension problems.
4, the different fuel assembly of three kinds of coolant channel diameters is arranged in fuel region, can effectively flatten power.
5, reflecting layer can effectively be enhanced neutron economy and be reduced reactor core using the MgO that reflecting properties are good and density is smaller
Quality.
6, reactor core control system and security system use innovative liquid control assembly, in control reactor core, ensure safety
On the basis of, effectively reduce the height of reactor core.
7, reactor core entire phase in longevity, thermal technology's limit value are set as fuel central temperature≤2000 DEG C, coolant channel surfaces highest
Temperature≤500 DEG C, coolant maximum flow rate≤1m/s, reduce the corrosiveness of LBE materials at high temperature.
The present invention effectively reduces heap core volume and quality, it can be achieved that on-board running, the operation of reactor core long-life are not reloaded, fortune
Power is evenly distributed in phase in row longevity, meets thermal technology's limit value, Core cooling agent bulkfactor, temperature coefficient, axial expansion and radial direction
The coefficient of expansion is negative value, has passive security characteristic.
Description of the drawings
Fig. 1 is honeycomb briquet type component gap section axial stratification schematic diagram.
Fig. 2 is Fig. 1 cross-sectional views along A-A.
Fig. 3 is coolant channel cross-sectional view.
Fig. 4 is reactor core cross-sectional view.
Fig. 5 is reflecting layer/shielded layer module transverse section schematic diagram.
Fig. 6 is reflecting layer/shielding layer assembly gap section axial stratification schematic diagram.
Fig. 7 is control assembly cross-sectional view.
Fig. 8 is the active regions control assembly B-B ievel cross section schematic diagram.
Fig. 9 is the connected regions control assembly C-C cross-sectional view.
Specific implementation mode
Structure of the invention is described in detail with reference to the accompanying drawings and detailed description.
As shown in Fig. 2, honeycomb briquet type fuel assembly of the present invention, the component section is hexagonal, and component is by component walls 1, cold
But agent channel 2 and fuel region 3 form, and are uniformly distributed 37 coolant channels in component, the coolant channel of three kinds of components is straight
Diameter is different,;It is calculated by optimization, reactor core assembly opposite side distance 10.0068cm, component wall thickness 0.2cm, coolant channel radius
0.258/0.288/0.328cm, coolant channel wall thickness 0.1cm, LBE covering thickness 0.1cm.This fuel assembly of reactor core display can
Meet maximum fuel central temperature≤2000 DEG C, maximum coolant channel wall temperature≤500 DEG C, coolant channel LBE maximums
Thermal technology's limit value of flow velocity 1m/s.
As shown in Fig. 2, the region in component walls 1, outside coolant channel includes in an axial direction:The fuel region 3 at middle part, fuel region
The fuel top air cavity 4 on 3 tops, the upper reflecting layer 5-1 on 4 top of fuel top air cavity, the lower reflecting layer 5-2 of 3 lower part of fuel region,
The upper cover 6-1 on the tops upper reflecting layer 5-1, the low head 6-2 of the lower reflecting layer lower parts 5-2.Upper cover 6-1 and low head 6-2 high
Degree is 5cm, upper reflecting layer 5-1 and lower reflecting layer 5-2 height 20cm, 3 height 85cm of fuel region, 4 height of fuel top air cavity warp
It crosses empirical formula calculating determination and takes 15cm;Entire fuel assembly height 150cm.
As shown in figure 3, the coolant channel of fuel region by fuel region coolant channel 7, fuel region coolant channel wall 8 and
LBE coverings 9 between fuel region coolant channel wall surface and fuel region form, and fuel region coolant channel is up and down.Fuel
When fuel is radially expanded, it is higher than fusing point when reactor core operation design LBE coverings between fuel region on the outside of area's coolant channel
LBE can be extruded in the cavity referred to above fuel, can effectively solve fuel and be radially expanded to squeeze fuel region coolant channel pipe
Pressure problem and optimization coolant take away the ability of fuel region heat.
As the preferred embodiment of the present invention, fuel region 3 use degree of enrichment for 19.75% UO2.
As the preferred embodiment of the present invention, fuel top air cavity 4 is interior filled with helium.
It is preferred that upper reflecting layer 5-1 compares the lower MgO of other reflecting material density with lower reflecting layer 5-2 materials, effectively drop
Low reactor core overall weight.
Upper cover 6-1 and low head 6-2 is T91 stainless steel materials.
As shown in figure 4, the small size long-life lead bismuth using honeycomb briquet type fuel assembly cools down fast reactor reactor core, reactor core cloth
Fuel area assembly 10, intermediate fuel area assembly 11, outer fuel area assembly 12, control assembly 13, security component 14, reflection are set
Layer assembly 15 and shielding layer assembly 16.10 coolant channel of fuel area fuel assembly maximum, intermediate fuel area fuel assembly
11 coolant channels take second place, fuel assembly 12 coolant channel in outer fuel area is minimum;Reactor core triangular arrangement various components, reactor core
The different fuel assembly of 3 kinds of coolant channel diameters is arranged in fuel region from inside to outside, it is radial by calculating effectively flattening reactor core
Power is distributed;Equivalent core diameter 100.24cm;Calculating core life can not reload continuous Operation at full power 18 years.
As shown in figure 5, the reflection layer assembly 15 of reactor core is identical with shielding 16 structure of layer assembly, section is hexagonal;Structure
Including shielded layer or reflecting layer component walls 17, shielded layer or reflecting layer coolant channel 18, coolant channel fill reflecting layer outside
19;Axial includes reflecting layer 19 and the upper low head 20 positioned at 19 top and the bottom of reflecting layer.Shielded layer or reflecting layer component walls 17 are thick
0.2cm, shielded layer or reflecting layer coolant channel 18 radius 0.3343cm, coolant channel wall thickness 0.1cm reflect layer assembly 15
It is evenly arranged 19 cooling ducts in shielding layer assembly 16;As shown in fig. 6, filling reflecting layer 19 outside coolant channel;It is axial
19 height of reflecting layer is 140cm, and 20 height of upper low head is 5cm.It reflects layer assembly 15 and shielding layer assembly 16 uses honeycomb briquette
Type can effectively enhance neutron reflection/shield effectiveness on the basis of not increasing assembly volume.
As shown in fig. 7, the control assembly 13 is liquid control assembly, 21 thickness of design control assembly wall is 0.3cm, stagnant
It is all mutually 85cm to stay area 22 and 23 height of fill area and fuel activity area height, and hexagon annulated column piston is designed between Li6 and Li7
24, indentation/suction sealing-plug 25 is designed above component, 26 thickness of T91 coverings is 0.1cm, and entire component design is multiple anti-
Area 27 is penetrated, the neutron economy of reactor core is enhanced, 28 height of cavity is 49cm, and control assembly coolant channel 29 up and down is thick
0.2cm is spent, stagnant area 22 is connected with fill area 23 by 12 perforations of liquid absorption material cylindrical channel 30.Liquid absorption material
Using the Li6 materials with larger fast neutron absorption cross-section;Liquid filling material uses Li7 materials.As shown in figure 8, not insert
Cross-sectional view of the control assembly 13 at Fig. 7 B-B under rodlike state, when indentation/suction sealing-plug 25 is by the Li6 on component top
Material is pressed into fill area 23 by stagnant area 22, and Li7 materials are pressed by cylindrical channel 30 as shown in Figure 9 in component
Between position stagnant area 22, the material for being detained to be come up by pressure is accommodated in cavity 28, is filled on the outside of component in the height of active region
Absorbing material reaches the function of absorbing neutron, control reactor core adjusting core power.Security component 14 has phase with control assembly 13
Same structure and material.
The present invention provides honeycomb briquet type fuel assemblies and small size long-life lead bismuth to cool down fast reactor reactor core, reactor core hot merit
Rate 20MW, do not reload continuously Operation at full power 18 years, vehicle-mounted can become one can remote accessible transport moving electric power
Production equipment, purposes are the power supply of population 10000 or so from far-off regions or military specific weapon continued power etc..Reactor core uses
Honeycomb briquet type fuel assembly, point 3rd area arrange three kinds of fuel assemblies, using honeycomb briquet type reflecting layer and shielding layer assembly, control system
System and security system are designed using liquid control assembly, effectively reduce the equivalent diameter and core height of reactor core, and reactor core is being run
Meet thermal technology's limit value in phase in longevity, control system and security system meet reactor core control and require, which has reactor core small, again
Amount is light, vehicle-mounted, long-life, safe feature can be achieved.
Claims (10)
1. a kind of honeycomb briquet type fuel assembly, is characterized in that:The fuel assembly includes that structure is identical but coolant channel diameter
Three kinds of different components, section are hexagonal;Structure includes component walls (1), and component walls (1) are interior evenly arranged in an axial direction cold
But agent channel (2), the region in component walls (1), outside coolant channel include in an axial direction:The fuel region (3) at middle part, fuel region
(3) the fuel top air cavity (4) on top, the upper reflecting layer (5-1) on fuel top air cavity (4) top, under fuel region (3) lower part
Reflecting layer (5-2), the upper cover (6-1) on upper reflecting layer (5-1) top, the low head (6-2) of lower reflecting layer (5-2) lower part.
2. honeycomb briquet type fuel assembly according to claim 1, it is characterised in that:The coolant channel of fuel region is by fuel
LBE between area's coolant channel (7), fuel region coolant channel wall (8) and fuel region coolant channel wall surface and fuel region
Covering (9) forms, and fuel region coolant channel is up and down.
3. honeycomb briquet type fuel assembly according to claim 1, it is characterised in that:The quantity of the coolant channel (2)
It is 37.
4. honeycomb briquet type fuel assembly according to claim 1, it is characterised in that:Fuel region (3) material is using rich
The UO2 that intensity is 19.75%;Filled with helium in fuel top air cavity (4);The upper reflecting layer (5-1) and lower reflecting layer
(5-2) material is MgO;The upper cover (6-1) and low head (6-2) material are T91 stainless steels.
5. a kind of small size long-life lead bismuth cools down fast reactor reactor core, it is characterised in that:Reactor core display fuel area fuel stack
Part (10), intermediate fuel area fuel assembly (11), outer fuel area fuel assembly (12), control assembly (13), security component (14),
Reflect layer assembly (15) and shielding layer assembly (16);It is characterized in that, fuel area fuel assembly (10), intermediate fuel
Area's fuel assembly (11) and outer fuel area fuel assembly (12) use honeycomb briquet type fuel assembly described in claim 1, knot
Three kinds of fuel assemblies that structure is identical but coolant channel diameter is different, fuel area fuel assembly (10) coolant channel maximum,
Intermediate fuel area fuel assembly (11) coolant channel takes second place, outer fuel area fuel assembly (12) coolant channel is minimum, subregion
Arrangement, can flatten the component power of reactor core;The reactor core triangular arrangement various components, most intermediate 1st circle of reactor core and the 2nd circle
7 fuel area fuel assemblies (10) are arranged altogether;3rd encloses uniformly 6 intermediate fuel area fuel assemblies (11) of alternate arrangement and 6
Control assembly (13);4th circle 18 intermediate fuel area fuel assemblies (11) of arrangement;In the position at the 5th hexagonal six angles of circle,
3 control assemblies (13) of alternate arrangement and 3 security components (14), control assembly (13) are in two with security component (14) position
Equilateral triangle is distributed;5th circle removes six Angle Positions, remaining arranges outer fuel area fuel assembly (12);6th six Angle Positions of circle
6 reflection layer assemblies (15) of arrangement, remaining arrangement outer fuel area's fuel assembly (12);The 7th reflection layer assembly of circle arrangement 36
(15);8th six Angle Position arranging shielding layer assemblies (16) of circle, remaining location arrangements reflect layer assembly (15);9th six angles of circle
Component is not arranged in position, and 42 shielding layer assemblies (16) are arranged in remaining position altogether.
6. small size long-life lead bismuth according to claim 5 cools down fast reactor reactor core, it is characterised in that:The shielded layer
Component (16) is identical as reflection layer assembly (15) structure, and section is hexagonal;Structure includes shielded layer or reflecting layer component walls
(17), shielded layer or reflecting layer coolant channel (18), coolant channel fill reflecting layer (19) outside;Axial includes reflecting layer
(19) and positioned at reflecting layer (19) top and the bottom upper low head (20).
7. small size long-life lead bismuth according to claim 5 cools down fast reactor reactor core, it is characterised in that:The control group
Part (13) is liquid control assembly, and structure includes control assembly wall (21), stagnant area (22), fill area (23), hexagon annulated column
Piston (24), indentation/suction sealing-plug (25), T91 coverings (26), echo area (27), cavity (28), control assembly coolant are logical
Road (29) and cylindrical channel (30);Control assembly wall (21) is regular hexagon structure, is wrapped on the outside of component;Coolant channel
(29) it is hexagon annulated column up and down;Cavity (28) is located at component central upper portion position, is hexagonal prisms structure, by T91 packets
Layer (26) closing;Stagnant area (22) is located at component upper outside position, between coolant channel (29) and component walls (21), is in
Hexagon annulated column shape;Fill area (23) is located at component lower outside, is hexagon annulated column structure, in component walls (21) and reflection
Between area (27), intermediate position setting is transitted to the Ring-cylindrical channel of empty cavity position by fill area (23), axial high with active region
Degree is consistent;Fill remaining component space in echo area (27);Indentation/suction sealing-plug of hexagon annulated column is arranged at stagnant area (22) top
(25);There are hexagon annulated column piston (24), isolation Li6 and Li7 materials in stagnant area (22) with fill area (23) contact surface;Stagnant area
(22) it is connected by 12 liquid absorption material cylindrical channel (30) perforations with fill area (23), cylindrical channel (30) is arranged in
Below module activity area height.
8. small size long-life lead bismuth according to claim 7 cools down fast reactor reactor core, it is characterised in that:The control group
The liquid absorption material of part (13) uses the Li6 materials with larger fast neutron absorption cross-section;Fill area (23) liquid is filled out
It fills material and uses Li7 materials;Security component (14) and control assembly (13) structure having the same.
9. small size long-life lead bismuth according to claim 5 cools down fast reactor reactor core, it is characterised in that:The heap in-core
There are coolant gap between the various assemblies of placement, the coolant uses LBE materials, the operation of reactor core normal pressure, outlet temperature
It is 500 DEG C.
10. small size long-life lead bismuth according to claim 5 cools down fast reactor reactor core, it is characterised in that:The reactor core
Equivalent diameter is 100.24cm, core height 150cm.
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Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103093837A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Accelerator-driven subcritical transmutation reactor core adopting dispersion metal fuel |
CN104183279A (en) * | 2014-08-26 | 2014-12-03 | 南华大学 | Inner-cooling pressurized-water reactor core |
CN105405475A (en) * | 2015-10-30 | 2016-03-16 | 西安交通大学 | Honeycomb-type fuel assembly and long-service-life supercritical carbon dioxide cooled reactor |
CN205428502U (en) * | 2015-11-05 | 2016-08-03 | 中国核动力研究设计院 | Small -size reactor of integration |
CN107408414A (en) * | 2015-04-02 | 2017-11-28 | 科利尔株式会社 | The power follower for shifting reflector thermal change using expansion principle minimizes nuclear power generating system |
-
2018
- 2018-04-19 CN CN201810354479.7A patent/CN108648834B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103093837A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Accelerator-driven subcritical transmutation reactor core adopting dispersion metal fuel |
CN104183279A (en) * | 2014-08-26 | 2014-12-03 | 南华大学 | Inner-cooling pressurized-water reactor core |
CN107408414A (en) * | 2015-04-02 | 2017-11-28 | 科利尔株式会社 | The power follower for shifting reflector thermal change using expansion principle minimizes nuclear power generating system |
CN105405475A (en) * | 2015-10-30 | 2016-03-16 | 西安交通大学 | Honeycomb-type fuel assembly and long-service-life supercritical carbon dioxide cooled reactor |
CN205428502U (en) * | 2015-11-05 | 2016-08-03 | 中国核动力研究设计院 | Small -size reactor of integration |
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