CN1700359A - Supercritical water nuclear reactor utilizing sleeve fuel assembly - Google Patents
Supercritical water nuclear reactor utilizing sleeve fuel assembly Download PDFInfo
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- CN1700359A CN1700359A CNA2005100553655A CN200510055365A CN1700359A CN 1700359 A CN1700359 A CN 1700359A CN A2005100553655 A CNA2005100553655 A CN A2005100553655A CN 200510055365 A CN200510055365 A CN 200510055365A CN 1700359 A CN1700359 A CN 1700359A
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Abstract
The invention relates to a super critical water nuclear reactor, which adopts external pipe fuel assembly in the field of nuclear reactor works technology. The external tube fuel assembly comprises concentric outer tube, inner tube and center tube, wherein the annular space between inner tube and center tube has unclear fuel element which has millimeter diameter and has UO2 small ball which is covered with multilayer SiC-PyC; inlet water enters into outer weir which is formed by outer tube and inner tube and then goes through inner tube and covering particle posited bed to directly cool covering particle, with the cooling water heated and gone through slotted hole of center tube and entered into center tube, at last dropped off center tube. It can adopt pressure shell type or design the outer tube into bearing pressure tube, which can bear super water designing pressure.
Description
Technical field
The invention belongs to the nuclear reactor field of engineering technology, be specifically related to a kind of supercritical water nuclear reactor that adopts the sleeve pipe fuel assembly.
Background technology
The operating pressure of supercritical water nuclear reactor is higher than the critical point 23MPa of water, water is single medium, water does not undergo phase transition in heap, and water temperature adopts direct thermodynamic cycle up to 510～620 ℃, thereby its net thermal efficiency can reach 45%, ratio light water reactor now exceeds 1/3, when being used to generate electricity, can save the uranium resource more than 30%, and simplified the configuration of water reactor to greatest extent, do not need steam generator, main circulation pump, voltage stabilizer, steam separator and exsiccator.Supercritical water core power station not only can utilize ripe light-water reactor technology, and conventional island can utilize the mature technology of supercritical thermal power factory fully.Estimate that in the world its cost can Da Dao $900/Kwe, cost of electricity-generating is ￠ 2.9/KWh, with China existing 1000Mwe pressurized-water reactor nuclear power plant target cost ($1300/Kwe) to compare with cost of electricity-generating (￠ 4.5/KWh), the range of decrease is very outstanding.Current, the international supercritical water reaction heap of developing mainly comprises following four kinds of schemes:
A. the similar presurized water reactor scheme of Tokyo University (pressure vessel pressurized, cluster fuel assembly);
B. heavy water slowing down CANDU type scheme (force pipe pressurized, cluster fuel assembly);
C. the SiC-PyC of U.S. PNNL clads UO
2Particle is fluidized-bed boiling-water reactor scheme in supercritical water;
D. the supercritical water fast neutron reactor can be used for the actinide that burns.
Two kinds of schemes of A, B adhere to pressure shell mould and pressure cast separately, but its fuel assembly is cluster, and fuel rod is with the UO about stainless steel or nickel-base alloy involucrum encapsulation diameter 1cm
2The cylindricality pellet.Chilled water absorbs the heat that the fuel element surface discharges from bottom to top by runner between rod in the option A, and temperature rises to core exit temperature.In the option b in the CANDU type reactor force pipe and interior cluster fuel assembly thereof place in horizontal direction, the chilled water along continuous straight runs is by runner between rod, force pipe has moderator D outward
2O.Because water temperature can be up to 500～620 ℃ in the supercritical water reaction heap, operating pressure is up to 25MPa, and (zirconium cladding encapsulates overall diameter 1cm left and right sides UO to widely used fuel rod in the existing water-water reactor
2Cylindricality pellet, inner inflatable) inapplicable, all need develop the fuel element of new cladding materials.
The overcritical water-water reactor scheme of U.S. PNNL is to have adopted supercritical water directly to cool off SiC-PyC cladding UO
2Granular fuel, but this scheme is to use the fluidized-bed heap of flow fuel.
In the supercritical water fast neutron reactor design of scheme D, remain and prolong the mentality of designing of having used rod cluster type fuel assembly.
Cladding particle UO
2Fuel element also has application in high temperature helium cooling graphite-moderated reactor.The ball bed high-temperature helium cooling graphite-moderated reactor of West Germany's initiative adopts the spheric fuel element of 6 centimetres of diameters, and several ten thousand cladding particles are sneaked into graphite substrate material, and the compacting balling-up has the thick solid graphite spherical shell of 5mm outward.Whole reactor core is formed one " fixedly ball bed " by spheric fuel element, does not have fuel assembly structure.The high temperature helium cooling graphite-moderated reactor of U.S.'s development adopts the column fuel assembly, and the cladding granular fuel is sneaked into graphite substrate material, is pressed into fuel compact rod (can be considered fuel element).Have 210 teaseholes and 108 cooling ducts on each hexagon graphite post xsect, both have loaded the fuel compact rod alternately in teasehole, form the column fuel assembly.This cladding granular fuel just is used for eight high temperature helium cooled reactors from the sixties in last century, comprises the 10MW thermal power high temperature helium cooling graphite moderating sphere bed test reactor that nuclear energy institute of Tsing-Hua University builds up.Nuclear energy institute of Tsing-Hua University made 44 batches of pebble bed reactor fuel elements altogether for building high temperature gas-cooled pebble bed reactor, and the cladding granular fuel is with UO
2(or mix with UC
2With fertile material ThO
2) be core, clad outside with which floor RESEARCH OF PYROCARBON and Si.In the above-mentioned high temperature helium cooling graphite-moderated reactor, cooling medium does not all directly contact this cladding granular fuel.
Summary of the invention
The object of the present invention is to provide a kind of system simple, thermal efficiency height, saving uranium resource, good economy performance, the supercritical water nuclear reactor of safe employing sleeve pipe fuel assembly.
Technical scheme of the present invention is as follows: the supercritical water nuclear reactor that adopts the sleeve pipe fuel assembly, comprise pressure vessel and place the interior reactor core of pressure vessel and control cluster mechanism, reactor core is made up of several sleeve pipe fuel assemblies, each sleeve pipe fuel assembly comprises coaxial outer tube, middle sleeve and pipe core, and the UO by multilayer SiC-PyC cladding of millimeter level diameter is housed in the annular space between middle sleeve and the pipe core
2The pellet shapes nuclear fuel element forms the cladding particle fixed bed of an annular, and outer tube top tube wall is provided with the inlet opening, is equipped with oval aperture on middle sleeve and the pipe core tube wall, and pipe core passes dividing plate and extends upward with the coolant outlet header box and link to each other; Import water flows into the outer flow passage that is made of outer tube and middle sleeve, radially pass oval aperture and cladding particle fixed bed on the middle sleeve tube wall, directly cooling cladding particle passes the oval aperture inflow pipe core on the pipe core tube wall after chilled water is heated, and flows out pipe core again.
Another kind of technical scheme of the present invention is: the supercritical water nuclear reactor that adopts the sleeve pipe fuel assembly, comprise box hat and place the interior reactor core of box hat and control cluster mechanism, reactor core is made up of several sleeve pipe fuel assemblies, each sleeve pipe fuel assembly comprises coaxial outer tube, middle sleeve and pipe core, and the UO by multilayer SiC-PyC cladding of millimeter level diameter is housed in the annular space between middle sleeve and the pipe core
2The pellet shapes nuclear fuel element, form the cladding particle fixed bed of an annular, outer tube is a pressure-bearing pipe that can bear overcritical water-water reactor design pressure, outer tube top is provided with the water inlet ozzle, be equipped with oval aperture on middle sleeve and the pipe core tube wall, and be provided with heat insulation layer with the upper center tube outside at active section, pipe core extends upward by the go out saliva header box of water delivering orifice ozzle with the heap top and is connected, control rod drive mechanisms (CRD) is installed in the top of box hat, and this box hat bears the corresponding design pressure of overcritical water-water reactor inlet water temperature degree; Import water flows into the outer flow passage that is made of outer tube and middle sleeve, radially pass oval aperture and cladding particle fixed bed on the middle sleeve tube wall, directly cooling cladding particle passes the oval aperture inflow pipe core on the pipe core tube wall after chilled water is heated, and flows out pipe core again.
Supercritical water nuclear reactor of the present invention has adopted the sleeve pipe fuel assembly, with the UO by multilayer SiC-PyC cladding of millimeter level diameter
2The pellet shapes nuclear fuel element places intermediate casing, and the high temperature supercritical water radially flows through fixedly ball bed of annular that the bead fuel element is piled at random with low speed, and cooling medium directly contacts this cladding granular fuel.Because the SiC-PyC cladding of fuel element has substituted traditional metal stainless steel cladding, significantly reduced parasitic absorption of neutron of stainless steel structure material.The cladding granular fuel is stochastic distribution and is piled into fixed bed in the sleeve pipe fuel assembly, and granule point contacts, and does not have the difficulty on the structural design.In addition, because the particles of nuclear fuel diameter is the millimeter level in the cladding particle, be generally 0.1～0.5mm, supercritical water reactor coolant flow is especially little, water flow velocity in runner is low, but heat release is fabulous in thimble assembly, and the temperature difference is not high between cladding granular fuel element surface coolant temperature and the cooling medium, so, UO
2The center of pellet temperature and the cladding granular fuel element surface cooling medium temperature difference and the maximum fuel center temperature difference are starkly lower than general water-water reactor analog value, the security that has improved overcritical water-water reactor greatly.The present invention substitutes and has exempted research and development and adapts to the high-performance metal involucrum rod shaped fuel element that such heap uses, and has shortened R﹠D cycle and research and development expense greatly.
Description of drawings
Fig. 1 is (pressure vessel pressure-bearing) sleeve pipe fuel assembly supercritical water pile structure synoptic diagram.
Fig. 2 is that the B-B of Fig. 1 is to view.
Fig. 3 is another structural representation of the overcritical water-water reactor of (pressure vessel pressure-bearing) sleeve pipe fuel assembly.
Fig. 4 is (pressure vessel pressure-bearing) sleeve pipe fuel assembly structure synoptic diagram.
Fig. 5 is the C portion enlarged drawing of Fig. 4.
Fig. 6 is the D portion enlarged drawing of Fig. 4.
Fig. 7 is that the B-B of Fig. 4 is to view.
Fig. 8 is (pipe pressure-bearing) sleeve pipe fuel assembly structure synoptic diagram.
Fig. 9 is that the B-B of Fig. 8 is to view.
Figure 10 is the structural representation with reactor core of rotation drive controlling rod.
1. pressure vessels, 2. reactor cores, 3. sleeve pipe fuel assemblies, 4. import aqua regions, 5. outlet aqua regions, 6. water inlet ozzles, 7. water delivering orifice ozzles, 8. bushing type ozzles, 9. outer tubes, 10. middle sleeves, 11. pipe cores, 12. cladding particle fixed bed 13. outer tubes (pressure-bearing pipe), 14. middle sleeves, 15. pipe cores, 16. cladding particle fixed beds, 17. rotation drive controlling rods among the figure
Embodiment
Below in conjunction with embodiment the present invention is described in further detail.
Embodiment one
As Fig. 1, shown in Figure 3, adopt among the supercritical water nuclear reactor embodiment of sleeve pipe fuel assembly at an electric power 250Mwe (thermal power 570Mwt), pressure vessel 1 is made by existing presurized water reactor mature technology, and structure is identical with the pressure vessel structure of existing presurized water reactor.Because the pressure vessel inwall only contacts import water (about 280 ℃), material can be used carbon steel, and stainless steel lining is arranged, and is provided with reactor core 2 and control cluster mechanism in the pressure vessel 1.The reactor core upper area is divided into upper and lower two parts by thermal baffle in the pressure vessel, and the bottom is an import aqua region 4, and top is outlet aqua region 5.Import water can adopt dual mode with the isolation that goes out saliva, and is a kind of for being respectively equipped with water inlet ozzle 6 that communicates with import aqua region 4 and water delivering orifice ozzle 7 (see figure 1)s that communicate with outlet aqua region 5 on the pressure vessel 1; Another kind is provided with bushing type ozzle 8 for pressure vessel 1, the water inlet ozzle of outer tube for communicating with import aqua region 4, and the water delivering orifice ozzle that interior Guan Weiyu outlet aqua region 5 communicates, the interior pipe outside is provided with the thermal insulation layer (see figure 3).Reactor core 2 is made up of several sleeve pipe fuel assemblies 3, as shown in Figure 4, each sleeve pipe fuel assembly comprises coaxial outer tube 9, middle sleeve 10 and pipe core 11, and the UO by multilayer SiC-PyC cladding of millimeter level diameter is housed in the annular space between middle sleeve 10 and the pipe core 11
2The pellet shapes nuclear fuel element, form the cladding particle fixed bed 12 of annular, outer tube 9 top tube walls are provided with circular inlet opening, be equipped with oval aperture on middle sleeve 10 and pipe core 11 tube walls, and being provided with heat insulation layer with the upper center tube outside at active section (cladding particle fixed bed part), pipe core 11 passes dividing plate and extends upward with the coolant outlet header box and link to each other.The shape of outer tube 9 can have different forms with the layout of control cluster.One, outer tube 9 and middle sleeve 10 are the circular zirconium alloy pipe that is suitable for inlet water temperature degree (280 ℃), pipe core 11 is for being suitable for exporting the circular stainless-steel tube or the nickel-based alloy pipe of coolant-temperature gage (540 ℃), outer tube 9 outer a branch of guide pipe that is used to insert control rod, the driving mechanisms of employing presurized water reactor typical case control cluster of being provided with; They are two years old, outer tube 9 is for being suitable for the hexagon zirconium alloy pipe of inlet water temperature degree (280 ℃), middle sleeve 10 is for being suitable for the circular zirconium alloy pipe of inlet water temperature degree (280 ℃), pipe core 11 is for being suitable for exporting the circular stainless-steel tube or the nickel-based alloy pipe of coolant-temperature gage (540 ℃), the control rod modes of emplacement adopts typical boiling-water reactor mode, promptly in the gap of outer tube control rod is set.Owing to the hexagon that is shaped as of outer tube, so the shape of control rod adopts the Y font.Above-mentioned multi-form control rod bottom all can have one section depleted uranium follower, not only can improve the reactor core transformation ratio, and can compensate the reactivity that burnup causes.As shown in figure 10, when being used for ship, ship, for reducing the pressure vessel height, the layout of control rod can also adopt following form: outside the core section, in the annulus of water reflection horizon, arrange the cylindrical control rod 17 of a circle, the part of rod is a stainless steel material, and remainder is for containing the sub-absorber of persistent erection (as B
4C) stainless steel material, and adopt the rotation of water-tight motor to drive this cylindrical control rod.The present invention can also adopt the burnable poison of various material of the prior art and form to control reactive and the flattening distribute power except that adopting control rod control reactivity.The UO by multilayer SiC-PyC cladding of millimeter level diameter
2The manufacturing process of pellet shapes nuclear fuel element is a mature technology now, in the sleeve pipe fuel assembly of manufacturing fuel pellet well directly can being packed into.
In the emergent pressure (23MPa) that surpasses water after the cooling medium of operation enters from the inlet nipple on pressure vessel top with 280 ℃ of temperature down, a small amount of by-pass flow flows into top and cavity of resorption respectively downwards and upwards, most of transcritical refrigerant enters reactor core top import aqua region 4, flow into the thimble assembly outer flow passage by the circular inlet opening on the outer tube 9 top tube walls, then by the radial direction crossing current of the oval aperture on middle sleeve 10 tube walls along pipe, pass between middle sleeve 10 and the pipe core 11 in the annular space the fixedly space of ball bed of fuel pellet, water is with after this cladding granular fuel directly contacts, when the oval aperture from pipe core 11 walls flows into center flow channels, 540 ℃ have been heated to, but it is single-phase that fluid is all the time, upwards flow into the coolant outlet header box by pipe core, and flow to the supercritical pressure turbine air intake opening by pressure vessel cooling medium water delivering orifice ozzle 7, constituted direct thermodynamic cycle.This supercritical water nuclear reactor can adopt boric acid and burnable poison to control reactivity, utilizes cladding granular fuel difference to add distribute power in concentration and the burnable poison flattening reactor core.The reflection horizon of arranging stainless steel and water around the reactor core can reduce the fast neutron radiation and the pressure vessel surface roentgen dose X of pressure vessel.
Embodiment two
Another embodiment of the invention is for adopting the supercritical water nuclear reactor of vertical pressure cast sleeve pipe fuel assembly, comprise box hat and place the interior reactor core of box hat and control cluster mechanism, reactor core is made up of several sleeve pipe fuel assemblies, the structure of sleeve pipe fuel assembly as shown in Figure 8, each sleeve pipe fuel assembly comprises coaxial outer tube 13, middle sleeve 14 and pipe core 15, and the UO by multilayer SiC-PyC cladding of millimeter level diameter is housed in the annular space between middle sleeve 14 and the pipe core 15
2The pellet shapes nuclear fuel element, form the cladding particle fixed bed 16 of an annular, outer tube 13 is the stainless steel pressure-bearing pipes that can bear overcritical water-water reactor design pressure, wall thickness is 6.6mm, be provided with a branch of zircaloy guide pipe that is used to insert control rod outside the outer tube 13, the control rod bottom can have one section depleted uranium follower.Outer tube 13 tops are provided with the water inlet ozzle, be equipped with oval aperture on middle sleeve 14 and pipe core 15 tube walls, and be provided with heat insulation layer with the upper center tube outside at active section (cladding particle fixed bed part), pipe core extends upward by the go out saliva header box of water delivering orifice ozzle with the heap top and is connected, import water flows into the outer flow passage that is made of outer tube 13 and middle sleeve 14, radially pass oval aperture and cladding particle fixed bed 16 on middle sleeve 14 tube walls, directly cooling clads particle, the oval aperture that passes after chilled water is heated on pipe core 15 tube walls flows into pipe core, flows out pipe core again.Control rod drive mechanisms (CRD) is installed in the top of box hat.The reflection horizon of arranging stainless steel and water around the reactor core can reduce the fast neutron radiation and the surperficial roentgen dose X of pressure vessel.As shown in figure 10, when being used for ship, ship, the layout of control rod can also adopt following form: outside the core section, in the annulus of water reflection horizon, arrange the cylindrical control rod 17 of a circle, the part of rod is a stainless steel material, and remainder is for containing the sub-absorber of persistent erection (as B
4C) stainless steel material, and adopt the rotation of water-tight motor to drive this cylindrical control rod.Stainless steel pressure-bearing pipe bears the pressure of 27.5Mpa in this programme, its box hat only need bear and the corresponding design pressure of overcritical water-water reactor inlet water temperature degree, the main effect of this box hat is under the loss of-coolant accident (LOCA) of pressure-bearing tracheal rupture, alleviates the reactor core dehydrating speed, the security under the raising accident.Because box hat need not to bear high pressure, so its wall thickness is far smaller than the presurized water reactor with power.
The supercritical water nuclear reactor of employing sleeve pipe fuel assembly of the present invention has a extensive future.Be used to build nuclear power station, its performance obviously is better than the supercritical water nuclear reactor that proposed, owing to adopt the cladding granular fuel, has avoided the development of stainless steel or nickel-base alloy involucrum fuel element; By modularization or pipe pressure-bearing type sleeve pipe fuel assembly supercritical water nuclear reactor, avoided high-power reactor to make the difficulty of major-diameter thick-wall pressure vessel.The complete available thermal power plant of conventional island supercritical steam turbine unit.This direct heating power thermal efficiency of cycle height (42～45%), cost low (expectation) is saved uranium (surpassing 30%), thereby realizes low electricity price.In addition, its system has simplified the equipment of water reactor to greatest extent, does not need steam generator, main circulation pump, voltage stabilizer, steam separator and exsiccator, has improved reliability and security greatly.Simultaneously, because full Natural Circulation, the cladding particle directly contacts with water, has increased inherent safety.Its thermal technology's margin of safety is big, burnup dark, neutron economy is good.And the feasibility of engineering-built is higher than other scheme of advanced heap of the 4th generation.
In order to solve the deficiency of uranium resource, China need develop fast breeder on the basis of overdevelopment neutron reactor, supercritical water can be used as the cooling medium of fast breeder, is guaranteeing to have improved fuel rating exponentially under safe heat release (margin of safety) condition.The doubling time and the fuel rating of nuclear fuel production are inversely proportional to, and therefore, the doubling time of nuclear fuel production shortens at double, are significantly shorter than the cold fast breeder reactor of sodium, have improved the performance of overcritical fast breeder.For being used for fast breeder reactor, can be with the sleeve pipe fuel assembly supercritical water fast neutron reactor module stack of high temperature supercritical water input that produces in the overcritical water-water reactor module of several thermal neutron sleeve pipe fuel assemblies, send into supercritical pressure turbine after overheated.The high temperature helium can be used as the cooling medium of fast breeder, the moderator that do not have in the heap, and the high temperature helium should directly contact the cladding granular fuel, and relatively reality is to adopt this sleeve pipe fuel assembly.In order further to improve the fast breeder thermal property, can improve operating pressure, at this moment adopt the sleeve pipe fuel assembly of pipe pressure-bearing to have more superiority, because it is little to the neutron economy performance impact to increase stainless steel material at this moment piling.
Claims (16)
1. supercritical water nuclear reactor that adopts the sleeve pipe fuel assembly, comprise pressure vessel (1) and place the interior reactor core (2) of pressure vessel (1) and control cluster mechanism, it is characterized in that: reactor core (2) is made up of several sleeve pipe fuel assemblies (3), each sleeve pipe fuel assembly comprises coaxial outer tube (9), middle sleeve (10) and pipe core (11), and the UO by multilayer SiC-PyC cladding of millimeter level diameter is housed in the annular space between middle sleeve and the pipe core
2The pellet shapes nuclear fuel element, form the cladding particle fixed bed (12) of an annular, outer tube (9) top tube wall is provided with the inlet opening, is equipped with oval aperture on middle sleeve (10) and pipe core (11) tube wall, and pipe core (11) passes dividing plate and extends upward with the coolant outlet header box and link to each other; Import water flows into the outer flow passage that is made of outer tube (9) and middle sleeve (10), radially pass oval aperture and cladding particle fixed bed (12) on middle sleeve (10) tube wall, directly cooling clads particle, the oval aperture that passes after chilled water is heated on pipe core (11) tube wall flows into pipe core, flows out pipe core again.
2. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 1, it is characterized in that: described outer tube (9) and middle sleeve (10) are for being suitable for the round tube of inlet water temperature degree material, pipe core (11) is for being suitable for exporting the round tube of coolant-temperature gage material, and being provided with heat insulation layer with the upper center tube outside at active section, outer tube is provided with a branch of guide pipe that is used to insert control rod outward.
3. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 1, it is characterized in that: described outer tube (9) is for being suitable for the hexagonal tube of inlet water temperature degree material, middle sleeve (10) is for being suitable for the round tube of inlet water temperature degree material, pipe core (11) is for being suitable for exporting the round tube of coolant-temperature gage material, and be provided with heat insulation layer with the upper center tube outside at active section, Y font control rod is set in the gap of outer tube.
4. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 1, it is characterized in that: outside the core section, in the annulus of water reflection horizon, arrange a circle cylindrical control rod (17), the part of rod is a stainless steel material, remainder is the stainless steel material that contains the sub-absorber of persistent erection, and adopts the rotation of water-tight motor to drive this cylindrical control rod.
5. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 1 is characterized in that: reactor core (2) upper area is divided into upper and lower two parts by thermal baffle, and the bottom is import aqua region (4), and top is outlet aqua region (5).
6. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 5 is characterized in that: be respectively equipped with water inlet ozzle (6) that communicates with import aqua region (4) and the water delivering orifice ozzle (7) that communicates with outlet aqua region (5) on the pressure vessel (1).
7. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 5, it is characterized in that: pressure vessel (1) is provided with bushing type ozzle (8), the water inlet ozzle of outer tube for communicating with import aqua region (4), the water delivering orifice ozzle that interior Guan Weiyu outlet aqua region (5) communicates, the interior pipe outside is provided with thermal insulation layer.
8. as the supercritical water nuclear reactor of claim 2 or 3 described employing sleeve pipe fuel assemblies, it is characterized in that: the control rod bottom can have one section depleted uranium follower.
9. as the supercritical water nuclear reactor of claim 2 or 3 or 4 described employing sleeve pipe fuel assemblies, it is characterized in that: except that adopting control rod, can also adopt the burnable poison of various materials and form to control reactive and the flattening distribute power.
10. as the supercritical water nuclear reactor of arbitrary described employing sleeve pipe fuel assembly in the claim 1～7, it is characterized in that: reactor core is provided with Stainless Steel Reflector of Core outward.
11. supercritical water nuclear reactor that adopts the sleeve pipe fuel assembly, comprise box hat and place the interior reactor core of box hat and control cluster mechanism, it is characterized in that: reactor core is made up of several sleeve pipe fuel assemblies, each sleeve pipe fuel assembly comprises coaxial outer tube (13), middle sleeve (14) and pipe core (15), and the UO by multilayer SiC-PyC cladding of millimeter level diameter is housed in the annular space between middle sleeve (14) and the pipe core (15)
2The pellet shapes nuclear fuel element, form the cladding particle fixed bed (16) of an annular, outer tube (13) is a pressure-bearing pipe that can bear overcritical water-water reactor design pressure, outer tube (13) top is provided with the water inlet ozzle, be equipped with oval aperture on middle sleeve (14) and pipe core (15) tube wall, and be provided with heat insulation layer with the upper center tube outside at active section, pipe core extends upward by the go out saliva header box of water delivering orifice ozzle with the heap top and is connected, control rod drive mechanisms (CRD) is installed in the top of box hat, and this box hat bears the corresponding design pressure of overcritical water-water reactor inlet water temperature degree; Import water flows into the outer flow passage that is made of outer tube (13) and middle sleeve (14), radially pass oval aperture and cladding particle fixed bed (16) on middle sleeve (14) tube wall, directly cooling clads particle, the oval aperture that passes after chilled water is heated on pipe core (15) tube wall flows into pipe core, flows out pipe core again.
12. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 11 is characterized in that: outer tube is provided with a branch of guide pipe that is used to insert control rod outward.
13. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 12 is characterized in that: the control rod bottom can have one section depleted uranium follower.
14. the supercritical water nuclear reactor of employing sleeve pipe fuel assembly as claimed in claim 11, it is characterized in that: outside the core section, in the annulus of water reflection horizon, arrange a circle cylindrical control rod (17), the part of rod is a stainless steel material, remainder is the stainless steel material that contains the sub-absorber of persistent erection, and adopts the rotation of water-tight motor to drive this cylindrical control rod.
15. the supercritical water nuclear reactor as claim 12 or 13 or 14 described employing sleeve pipe fuel assemblies is characterized in that: except that adopting control rod, can also adopt the burnable poison of various materials and form to control reactive and the flattening distribute power.
16. as the supercritical water nuclear reactor of arbitrary described employing sleeve pipe fuel assembly in the claim 11～14, it is characterized in that: reactor core is provided with Stainless Steel Reflector of Core outward.
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| CN101727992B (en) * | 2009-11-23 | 2011-12-28 | 中国核动力研究设计院 | Sleeve pipe type low-enriched uranium nuclear fuel assembly |
| CN102354539A (en) * | 2011-09-15 | 2012-02-15 | 西安交通大学 | Annular fuel element and annular fuel supercritical water reactor |
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| DE1514462A1 (en) * | 1965-05-19 | 1969-08-28 | Siemens Ag | Fuel element for nuclear reactors |
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| DE3604869A1 (en) * | 1986-02-15 | 1987-08-20 | Hochtemperatur Reaktorbau Gmbh | GAS-COOLED CORE REACTOR WITH A STATIONARY PROTECTION OF SPHERICAL OPERATING ELEMENTS |
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| FR2807563B1 (en) * | 2000-04-07 | 2002-07-12 | Framatome Sa | NUCLEAR FUEL ASSEMBLY FOR A LIGHT WATER-COOLED REACTOR COMPRISING A NUCLEAR FUEL MATERIAL IN THE FORM OF PARTICLES |
| JP2003294878A (en) * | 2002-04-03 | 2003-10-15 | Yoshiaki Oka | Fuel assembly |
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