CN104167226B - Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test - Google Patents
Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test Download PDFInfo
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- CN104167226B CN104167226B CN201410453769.9A CN201410453769A CN104167226B CN 104167226 B CN104167226 B CN 104167226B CN 201410453769 A CN201410453769 A CN 201410453769A CN 104167226 B CN104167226 B CN 104167226B
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test. The liquid metal cooling reactor experimental system consists of a safety vessel (1), a main vessel (2), a reactor inner supporting structure (3), a reactor core (4), a central measuring column (5), a main heat exchanger (6), a reloading mechanism (7), a reactor top cover (8), a control bar drive mechanism (9) and a neutron source (10); when the critical running test is performed, the neutron source (10) adopts a californium-252 neutron source or a Be-Am neutron source; when the subcritical running test is performed, the neutron source (10) adopts a spallation neutron source or a deuterium tritium neutron source, an isotopic neutron source and a fuel component in the middle part of the reactor core are replaced by an accelerator neutron source according to the real requirement of the spallation neutron source, and the reactor can have the subcritical running test. The reactor experimental system is naturally and circularly cooled by adopting liquid lead-bismuth or lead, so that the usability of the reactor can be improved, the experimental cost can be reduced, and the multifunctional reactor experimental system characteristics can be achieved.
Description
Technical field
The invention belongs to reactor experimental system design technical field, specific design is a kind of to can achieve critical and subcritical fortune
The liquid heavy metal natural circulation cooling reactor experimental system of row experiment.
Background technology
Liquid-metal cooled reactor structure is simple, and all coolants are all in a container, it is to avoid occur primary Ioops cold
But (loca) accident is lost in agent, can effectively improve the safety of reactor, be important candidate's heap-type of advanced reactor.In state
In six kinds of the 4th generation of technology such as nuclear energy system that border International Atomic Energy Agency (iaea) issues, sodium-cooled fast reactor and Lead cooled fast breeder reactor belong to liquid metal
Cooled reactor.In Accelerator Driven Subcritical reactor (ads) design, it is also adopted by liquid-metal cooled reactor.
Liquid-metal cooled reactor experimental system is the necessary system equipment of liquid-metal cooled reactor technology development.
More increase particularly with meaning for the research of the Lead cooled fast breeder reactor being still in the conceptual approach stage and Accelerator Driven Subcritical heap
Greatly.By reactor experimental system, neutronics, thermohydraulics and the security feature of novel reaction heap, Ke Yikao can be verified
Test the fuel needed for novel reaction heap and material property, design, construction and the operating experience of reactor can be accumulated.
Liquid-metal cooled reactor can be divided into critical pile and subcritical reactor according to operational mode, according to routine
Design, for the reactor of different operational modes, needs to build critical pile experimental system and convergent reaction respectively
Heap experimental system and subcritical reactor experimental system.Reactor experimental system, according to power level, can be divided into cold conditions zero energy
Experimental provision hot Power operation assay device.
China Atomic Energy Science Research Institute is the zero energy critical assembly (east wind that developmental threshold fast reactor technology is built
6), a zero energy subcritical assembly (Venus) for development Accelerator Driven Subcritical heap technology construction and Belgium
Sck cen research institution is the zero energy subcritical assembly that development Accelerator Driven Subcritical device is built
(guinevere) belong to cold conditions zero power assembly.Belgian sck cen research institution is development ads Technology design
The 100mw reactor myrrha and 80mw-xads that Italian enea research institution is development ads Technology design belongs to liquid power
Operating test device, reactor can only carry out subcritical operation test.
To realize critical operation experiment and subcritical running experiment in same reactor system, changing of system need to be resolved
Make problem, required with meeting different service conditions.In currently running reactor system, such as presurized water reactor and sodium-cooled fast reactor,
Due to the restriction of special service condition, very big to the transformation difficulty of reactor core and reactor system.It is high pressure during water pressuring stacking operation
Environment, sealing for pressure vessels and integrity demands are very high, are not suitable for being transformed into from the extraneous subcritical system introducing neutron source
System.Sodium-cooled fast reactor has seal request when running, and prevents Liquid Sodium and air contact from producing sodium fire, is also not suitable for being transformed into from outer
Boundary introduces the subcritical system of neutron source.
The density of the general fuel assembly of density ratio of liquid heavy metal is high, and fuel assembly needs using being mechanically fixed in heap
Mode, to avoid the fuel assembly problem brought of floating.And the mode being mechanically fixed can under high-temperature liquid state heavy metal environment
Can be due to losing efficacy the problems such as irradiation and corrosion.The macroscopic density of assembly is made to be more than cooling using increasing high density weight material
Agent density can achieve inherently safe.
The reactor of different operational modes is different due to reactor core display, and core power density difference is big, and it is suitable to be difficult to realize
Assignment of traffic, core exit temperature inhomogeneous broadening effect substantially, the safety problem that may result in some overheating components and bring.
Can achieve that difference inter-module is distributed by practical situation using the assignment of traffic self-regulation effect that the density contrast of liquid heavy metal brings
Flow.
Institute of Chinese section starts the Chinese Academy of Sciences strategic guide science and technology special project " following advanced nuclear fission energy-ads within 2011
Transmuting system ", the enforcement by three phases for the plan, it is respectively completed ads research device, ads experimental provision and ads demonstration plant
Be built in experimentation, build up ads transmuting Industrial demonstration system to after the year two thousand thirty, grasp the crucial skill that nuke rubbish transmuting is processed
Art, makes the capability of independent innovation in advanced nuclear energy field for the China enter ranks advanced in the world.One kind involved in the present invention can be real
The liquid-metal cooled reactor experimental system of existing critical and subcritical running experiment can carry out ads system and Lead cooled fast breeder reactor technology
Experiment, is ads technical research and China's liquid metal cooled fast heap research provides Important Platform.
Content of the invention
The technical problem that the present invention overcomes: overcome the deficiencies in the prior art, a kind of achievable critical and subcritical fortune is provided
The liquid-metal cooled reactor experimental system of row experiment, can carry out critical operation experiment in same set of experimental system and face with secondary
Boundary's running experiment, when carrying out critical operation experiment, neutron source adopts californium -252 or be-am isotope neutron source, and reactor can
Carry out critical operation experiment；When carrying out subcritical running experiment, neutron source adopts spallation neutron target, according to spallation neutron target
It is actually needed and the isotope neutron source in the middle part of reactor core and fuel assembly are substituted for accelerator neutron generator, reactor can enter places and face
Boundary's running experiment.This reactor experimental system can realize critical operation and subcritical operation by changing different neutron sources, carries
The high availability of reactor, reduces experimental cost, possesses polyfunctional reactant heap and realize system performance.
A kind of technical solution of the present invention: liquid metal cooling reaction that can achieve critical and subcritical running experiment
Heap experimental system, by safety container, primary tank, heap inner supporting structure, reactor core, center measurement column, main heat exchanger, refueling agency,
Heap top cover, CRDM and neutron source composition.Described safety container and primary tank are the bilayer of similar water bottle liner type
Structure, described heap top cover is flat cover form, is arranged on the upper edge of primary tank, described refueling agency is arranged in heap top cover
Heart position, four described main heat exchangers are installed in the annular region of heap top cover, and described heap inner supporting structure is welded in master
Position more than container bottom (head), provides for reactor core and supports and position, and described neutron source is located at reactor core center position, adopts
With reactor core identical fuel assembly form, described center measurement column is welded in the bottom of refueling agency main body, positioned at reactor core
Top；When carrying out critical operation experiment, neutron source adopts isotope neutron source, and positioned at reactor core center, reactor is in and faces
Boundary's operational mode；When carrying out subcritical running experiment, neutron source adopts accelerator bombardment spallation target to provide neutron source, positioned at heap
Core center, extracting part exceptionally encloses fuel assembly, makes reactor be in subcritical operational mode.
Wherein, reactor has from critical to subcritical, dual mode operated ability；Changed by double whirl-plug rocker-arm remote operating
Interior for reactor core one layer of fuel assembly and isotope neutron source are extracted out by material mechanism, by out-pile mechanically actuated apparatus by heap top cover
Accelerator neutron generator insertion reactor core reserving hole channel, until subcritical neutron source bottom be located at reactor core center, realize run
Patten transformation.
Wherein, assembly flow quantity self-adjusting section effect, heap in-core coolant flow can be realized by way of natural circulation cooling
Distribution relies on the different density variation that produces of the power of assembly to realize, and achievable core exit temperature homogenization avoids strong simultaneously
Urgent convection current drives the unstability impact that reactor core assembly is brought.
Described reactor experimental system adopts modularized design, by refueling agency by interior for reactor core one layer of fuel assembly and
Critical source is extracted out, and subcritical neutron source is passed through the reserving hole channel insertion reaction in cock by out-pile mechanically actuated apparatus
Heap, until subcritical neutron source bottom is located at reactor core center, realizes operational mode conversion.
Described reactor experimental system heap top cover is in ring-like with one heart, is made up of large rotating plug and pet cock, part adopts module
Change design, duct is left at large rotating plug center, for installing subcritical neutron source.
Described reactor experimental system reactor core is made up of replaceable fuel assembly, and fuel assembly can adopt hexagon fuel
Assembly.
Described reactor experimental system neutron source is designed with critical source and two sets of parts of subcritical neutron source, critical in
Component can adopt 252Cf neutron source, and subcritical neutron source can adopt Accelerator driven spallation target neutron source.
The innovative point of the present invention is:
(1) reactor experimental system of the present invention adopts modularized design, can be realized same by changing different neutron sources
Critical operation experiment and subcritical running experiment are carried out on one block response heap experimental system, improve reactor experimental system can
With property, reduce experimental cost, possess polyfunctional reactant heap experimental system characteristic.
(2) coolant system of the present invention adopts lead bismuth alloy or lead natural circulation cooling, can achieve difference reactor core display bar
Flow quantity self-adjusting section under part, obtains uniform outlet temperature, and forced convection can be avoided to drive, and the assembly that leads to is unstable asks simultaneously
Topic.
(3) present invention is by being replaced with accelerator neutron generator scheme by fuel assembly in the middle part of isotope neutron source and reactor core,
Realize from critical operation experimental system to the conversion of subcritical running experiment system.
Brief description
Fig. 1 is the longitudinal direction figure of critical operation experiment of the present invention；
Fig. 2 is the transverse view of critical operation experiment of the present invention；
Fig. 3 is the longitudinal direction figure of the subcritical running experiment of the present invention；
Fig. 4 is the transverse view of the subcritical running experiment of the present invention.
Specific embodiment
Below in conjunction with the accompanying drawings and specific embodiment further illustrates the present invention.
As shown in figure 1, a kind of liquid metal cooling that can achieve critical and subcritical running experiment that the present invention provides is instead
Answer heap experimental system, by safety container 1, primary tank 2, heap inner supporting structure 3, reactor core 4, center measurement column 5, main heat exchanger 6, change
Material mechanism 7, heap top cover 8, CRDM 9 and neutron source 10 form.
Safety container 1 is made up of with bottom bulkhead cylindrical housings, similar to primary containment structure, and its function is in primary tank
When there is leakage, safety container will contain primary Ioops coolant, and ensure that in primary tank, lead bismuth liquid level enters higher than afterheat heat exchanger
Mouthful window is it is ensured that residual heat removal system normal work.Space between safety container and primary tank, is filled with argon protection, installs
There are lead bismuth leak detector, pressure detecting and overpressure protection system, safety detection is carried out by distant behaviour's equipment.
Primary tank 2 is a cylindrical vessel being welded with ellipse end socket by cylindrical housings, and side wall does not pass through
Wear part.Primary tank contains primary Ioops coolant and blanketing gas, supports in-pile component, prevents the radioactive substance that nuclear reaction produces
Leak.Equipped with heat shielding and hot lead bismuth pond between inside primary tank, and by ad hoc passage, it is cooled down.
Horizontally disposed plate is formed by connecting by heap inner supporting structure 3 cylinder and conically shaped, is fixed by welding in primary tank
Bottom, in order to ensure the rigidity of structure, installs radial floor additional in heap inner supporting structure.Heap inner supporting structure is mainly in order to support
Reactor diagrid, forms the lateral boundaries of reactor core inlet chamber, and core region and reactor core upper area are separated with main heat exchanger region,
Contain reactor core and refuelling system in heap.The inner ring of heap inner supporting structure is outwards outwardly recessed a region and reloads lifting for installation
Machine.
Reactor core 4 is made up of replaceable fuel assembly, and fuel assembly can adopt hexagonal fuel assembly or tetragon fuel
Assembly, when carrying out subcritical operation test, parts replaceable one-tenth spallation target in reactor core.
Center measurement column 5 is the cylindric welded case with dished (torispherical) head, and horizontal grid plate and conduit, position are installed in inside
Center below cock, is split-type design, and its main part is welded on large rotating plug, and partial sector areas are welded on
On pet cock.Control rod guiding mechanism and thermocouple conduit are welded with the measurement column of center, for location control rod conduit lifting
Mechanism and measuring system.
The outside of main heat exchanger 6 is sleeve pipe, predominantly fixing and support main heat exchanger.Lead bismuth entrance is left on sleeve pipe
Window is corresponding with the inlet window of main heat exchanger
Reactor passes through the difference in height of reactor core 4 and main heat exchanger 6, and the density contrast of lead bismuth coolant, provides pressure head real
The type of cooling of existing Natural Circulation.Due to the density p=11367-1.1944*t of lead bismuth, increase density with temperature and substantially reduce,
The assignment of traffic of Natural Circulation can be carried out by the density contrast of reactor core 4 different fuel component power.
The equipment that refueling agency 7 comprises has: elevator in refueling machine and heap in double whirl-plug (large rotating plug and pet cock), heap
Deng.Large rotating plug is concentric with heap top cover to be installed, and pet cock is eccentrically mounted with large rotating plug, and refueling machine is arranged on pet cock eccentric position,
Big pet cock forms three-level toggle with refueling machine and its mechanical arm, to carry out reloading in reactor.Reload in heap and be
System, is capable of realizing in high-temperature lead bismuth environment the handling behaviour of heap fuel assembly in the case that reaction vessel completely encloses
Make.The passage entering reactor for proton beam system is left at the center of large rotating plug simultaneously, is filled out using shield in critical operation
Fill.
In the form of flat cover, overall be in ring-like with one heart to heap top cover 8.The large rotating plug that reloads is located at heap top cap central position, uses
In reloading, and provide positioning for CRDM, measuring system etc. and support.Large rotating plug passes through thrust ball axle by top cover
Hold and supported.The supporting structure of 4 main heat exchangers is symmetrical two-by-two on heap top cover top.A sky between main heat exchanger
Remaining position is the lifting hole that reloads.
CRDM 9 is made up of two sets of control rod driving structures, and first set reactivity control system is by regulating rod
Assembly, compensation rod assembly and its CRDM composition.Adjust rod assembly and compensate rod assembly all using ball-screw-silk
Female pair formula CRDM.Second set controls bar system to utilize control rod in the buoyancy of lead solution, completes emergency shut-down
Task.
As shown in Fig. 2 the transverse view tested from critical operation, when carrying out subcritical running experiment, neutron source 10
Positioned at reactor core centre position, using californium -252 or the be-am neutron source of hexagon kit form.
Main heat exchanger 6 is long round section, being capable of space between effectively utilizes reactor core and container.Four main heat exchangers 6
In reactor, 90 ° are uniformly distributed, and can effectively ensure that in reactor, temperature field and Flow Field Distribution are uniform.
As shown in figure 3, from the longitudinal direction figure of subcritical running experiment, when carrying out subcritical running experiment, neutron source
10 adopt spallation neutron target or deuterium tritium neutron source, through heap top cover 8, insert reactor core 4 center vertically from above.
As shown in figure 4, from the transverse view of subcritical running experiment, when carrying out subcritical running experiment, by reactor core 4
Interior one layer of fuel assembly and isotope neutron source are extracted out, by accelerator neutron generator insertion reactor core 4 preformed hole in heap top cover 8
Road, until subcritical neutron source bottom is located at reactor core 4 center, realizes operational mode conversion.
Claims (1)
1. a kind of liquid-metal cooled reactor experimental system that can achieve critical and subcritical running experiment it is characterised in that:
This reactor experimental system is by safety container (1), primary tank (2), heap inner supporting structure (3), reactor core (4), center measurement column
(5), main heat exchanger (6), refueling agency (7), heap top cover (8), CRDM (9), and neutron source (10) composition；Described
Safety container (1) and primary tank (2) be the double-decker of similar water bottle liner type, described heap top cover (8) is flat cover form, peace
It is contained in the upper edge of primary tank (2), described refueling agency (7) is arranged on the center of heap top cover (8), and the master described in four changes
Hot device (6) is installed in the annular region of heap top cover (8), and described heap inner supporting structure (3) is welded in primary tank (2) bottom (head)
Above position, is that reactor core (4) provides and supports and position, described neutron source (10) is located at reactor core center position, using with
Reactor core identical fuel assembly form, described center measurement column (5) is welded in the bottom of refueling agency (7) main body, positioned at heap
The top of core (4)；When carrying out critical operation experiment, neutron source (10) adopts isotope neutron source, positioned at reactor core (4) center
Place, reactor is in critical operation pattern；When carrying out subcritical running experiment, neutron source (10) adopts accelerator neutron generator,
Positioned at reactor core (4) center, extracting part exceptionally encloses fuel assembly, makes reactor be in subcritical operational mode；
The outside of main heat exchanger (6) is sleeve pipe, predominantly fixing and support main heat exchanger, and sleeve pipe leaves lead bismuth entrance
Window is corresponding with the inlet window of main heat exchanger；
Reactor passes through the difference in height of reactor core (4) and main heat exchanger (6), and the density contrast of lead bismuth coolant, provides pressure head real
The type of cooling of existing Natural Circulation, substantially reduces because the density with temperature of lead bismuth increases density, can be different by reactor core (4)
The density contrast of fuel assembly power carries out the assignment of traffic of Natural Circulation；
Reactor has from critical to subcritical, dual mode operated ability；By double whirl-plug rocker-arm remote operating refueling agency (7)
Interior for reactor core (4) one layer of fuel assembly and isotope neutron source are extracted out, by out-pile mechanically actuated apparatus by heap top cover (8)
Accelerator neutron generator insertion reactor core (4) reserving hole channel, until subcritical neutron source bottom is located at reactor core (4) center, real
Existing operational mode conversion；
Described reactor experimental system adopts modularized design, in critical operation, the hole that can reserve from top cover large rotating plug
Road, using modularity shield by center hole plug, in subcritical operation, takes out shield, is changed to subcritical neutron source and makees
For part, insertion reaction heap, up to reactor core center；
Described reactor experimental system neutron source is designed with critical source and two sets of parts of subcritical neutron source, critical source
252Cf neutron source or be-am neutron source can be adopted, subcritical neutron source can adopt Accelerator driven spallation target neutron source or deuterium
Tritium neutron source；
This can achieve that the liquid-metal cooled reactor experimental system of critical and subcritical running experiment adopts modularized design, can
Realize critical operation experiment and subcritical operation are carried out on same block response heap experimental system by changing different neutron sources
Experiment, improves the availability of reactor experimental system, reduces experimental cost, possesses polyfunctional reactant heap experimental system special
Property；
This can achieve that the liquid-metal cooled reactor experimental system coolant system of critical and subcritical running experiment adopts lead
Bismuth alloy or lead natural circulation cooling, can achieve the flow quantity self-adjusting section under the conditions of difference reactor core display, obtain uniform outlet temperature
Degree, can avoid the assembly instability problem that forced convection driving leads to simultaneously；
This can achieve that the liquid-metal cooled reactor experimental system of critical and subcritical running experiment is passed through isotope neutron
In the middle part of source and reactor core, fuel assembly is replaced with accelerator neutron generator scheme, realizes from critical operation experimental system to subcritical operation
The conversion of experimental system.
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