CN104409109A - Ultrahigh specific power thermal neutron thorium breeder reactor apparatus and method for nuclear fuel propagation - Google Patents
Ultrahigh specific power thermal neutron thorium breeder reactor apparatus and method for nuclear fuel propagation Download PDFInfo
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- CN104409109A CN104409109A CN201410504743.2A CN201410504743A CN104409109A CN 104409109 A CN104409109 A CN 104409109A CN 201410504743 A CN201410504743 A CN 201410504743A CN 104409109 A CN104409109 A CN 104409109A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
- G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
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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
Abstract
The invention relates to an ultrahigh specific power thermal neutron thorium breeder reactor apparatus, the apparatus comprises a reactor core which is a set of fan-shaped sheet type graphite fuel pebble-bed; a high temperature liquid metal heat-carrying agent central flow channel which is positioned at center of a thermal neutron thorium propagation device; a low temperature liquid metal heat-carrying agent decreasing flow channel which is positioned at outside of the reactor core; a graphite reflection layer as a hollow circle structure, wherein the graphite reflection layer is capable of encircling four sides of the reactor core and the decreasing flow channel for the low temperature liquid metal heat-carrying agent; a molten salt propagation layer which is a graphite fan-shaped hollow structure, wherein thorium-containing molten salts filled in cavity can be taken as a core fertilizer, and the molten salt propagation layer and the graphite reflection layer enable cross arrangement; a Bi-Li extractor positioned outside the molten salt propagation layer; and a Bi-Li extractor connection pipeline, which is connected to a Pa-233 storage decay separator outside a pile. According to the invention, fuel spheres can be operated under ultrahigh specific power, and the method enables propagation of U-233 nuclear fuel under high speed with less than 4 years of fuel multiplication period.
Description
Technical field
The invention belongs to nuclear energy technology field, refer to a kind of method of superelevation specific power thermal neutron thorium breeder device and fertile nuclei fuel especially.
Background technology
China's rare earth resources enriches, and turnout occupies first of the world.China rare earth mineral reserve concentrate on Inner Mongolia again, owing to being with radioactive thorium element containing a large amount of in slag, the latter there is no and obtains large-scale industrial use, and overstock for a long time, pile up like a mountain, cause Heavy environmental pollution, particularly after groundwater contamination, more may threaten Lower Reaches of The Yellow River, cause compatriots worried, urgent expectation is used, and just evil is for precious.The performance although thorium element itself is not fissioned, but after it absorbs neutron, artificial fissilenuclide U-233 can be generated, there are the some performances being better than natural fission nuclide U-235, the secondary neutron number that such as its fission with thermal neutron produces is 2.3, higher than 2.05 of U-235, thus Nuclear fuel breeding may be realized in thermal-neutron reactor, therefore world's nuclear power development history once starting a burst of " utilization of thorium " upsurge: in generation U.S.'s nineteen fifty, successively builds up the thorium proliferation test heap MSRE achieving and adopt liquid molten salt fuel, with the Shipping-port thorium propagation presurized water reactor adopting rod shape fuel, Germany also builds up THTR thorium propagation pyrographite pebble bed reactor in generation nineteen ninety.
But the utilization of thorium is all in the exploratory stage in countries in the world, and unlike large nuclear power station, possesses the mature technology of commercialization introduction.And also have some key problem in technology being difficult to break through to there is no the approach of solution.Therefore, there is not the ripe road that leads to liquid fuel thorium breeder at present in the world.
Inventor proposes the patented claim of " method of the inherently safe production high-temperature nuclear energy of high-power self-operating " that possess natural safety energy in April, 2010, and obtains Intellectual Property Right in China office duly authorized (ZL201010145086.9) in August, 2012.This not long ago, within 2011, inventor also obtains the mandate (#ZL200810105349.6) of another patent of invention " method and apparatus of fast breeding and converting nuclear fuel ", wherein specifies and how to pass through to improve the technological improvement direction that specific nuclear fuel power shortens the fuel-doubling time of all kinds of neutron multiplication heap greatly.In January, 2013, inventor proposes again the new invention of " method of all-round uranium-thorium conversion-breeder reactor device and production nuclear fuel uranium-233 ", solve the severe contamination that aforementioned (1) reactor core and whole primary Ioops equipment are subject to radioactive fission fragment, and (2) Nuclear fuel breeding this two large technical barrier more long than very little and phase of doubling.This number of patent application is 201310011868.7, and industry was announced on May 8th, 2013, entered the substantive examination stage.In order to improve growth rate further, another patented claim 201310334268 is also proposed for 2013, " utilizing thorium to produce fast breeder system base and the enrichment procedure of nuclear fuel ".In above-mentioned domestic existing technical foundation, the fuel rating that conceptual design at that time can reach can reach 10MW/kg, and the corresponding fuel multiplication phase is 6 years, seems to reach technological limit.Thereafter, in order to challenge this limit, inventor is again through the research of nearly 1 year, and people proposes greatly to shorten further this " limit " further, makes the fuel multiplication phase utilizing thorium to produce the thermal neutron fast breeder system of nuclear fuel shorten to less than 2 years lower level new inventions as follows.
Summary of the invention
The object of the present invention is to provide a kind of method of superelevation specific power thermal neutron thorium breeder device and fertile nuclei fuel, its be most economical thorium utilize technology, wherein adopt the liquid metal catalyst carrier that heat transfer property is superb, cooling comprises the graphite fuel ball of nuclear fuel coated particle, fuel sphere is run under superelevation specific power, with the high speed propagation U-233 nuclear fuel of fuel less than 4 years phase of multiplication.
The invention provides a kind of superelevation specific power thermal neutron thorium breeder device, comprise:
One reactor core, this reactor core is one group of fan-shaped sheet graphite fuel ball bed;
One high temperature fluent metal catalyst carrier center flow channels, for deriving fission and the nuclear energy of reactor core production, this high temperature fluent metal catalyst carrier center flow channels is positioned at the center of thermal neutron thorium proliferation device;
One low temperature liquid metal catalyst carrier decline runner, this decline runner is positioned at the outside of reactor core;
One graphite reflector, this graphite reflector is hollow circular structure, from four sides up and down around the low temperature liquid metal catalyst carrier decline runner in reactor core and outside thereof;
One molten-salt breeder layer, this molten-salt breeder layer is a graphite fan blades shape hollow structure, is full of thoriated and melts salt as core fertilizer, this molten-salt breeder layer and graphite reflector cross arrangement in cavity wherein;
One Bi-Li extractor, this Bi-Li extractor is the extraction equipment of core fertilizer thorium and Pa-233 after irradiation, is positioned at the outside of molten-salt breeder layer;
One Bi-Li extractor connecting tube, stores with the Pa-233 of out-pile the separation vessel that decays and is connected, and storing Pa-233 decay in decay separation vessel at Pa-233 is U-233.
The present invention also provides a kind of method of superelevation specific power thermal neutron thorium breeder fertile nuclei fuel, the method adopts foregoing device, liquid metal is wherein adopted to cool the graphite pebble bed core that comprises coated particle nuclear fuel, nuclear fuel is run under more than the superelevation specific power of 20MW/kg, its fuel multiplication phase reduces to less than 2 years, and the method comprises the steps;
Step 1: carry out fission reaction, productional surplus neutron at a reactor in-core using uranium as nuclear fuel;
Step 2: in a graphite reflector, make the residue moderation of neutrons leaking out reactor core, a part returns reactor core, reduces its critical mass, and a part is to external leakage, and the molten-salt breeder layer entering thoriated fused salt produces new nuclear fuel;
Step 3: at one using thorium as in the molten-salt breeder layer of core fertilizer, makes thorium capture neutron and produces Pa-233;
Step 4: the Pa-233 in the thoriated fused salt after irradiation is separated with thoriated fused salt with in Bi-Li extractor by core fertilizer thorium after an irradiation;
Step 5: store in decay separation vessel at Pa-233 and Pa-233 is decayed for U-233 and in addition Separation & Purification;
Step 6: in a nuclear fuel preparation facilities, the U-233 after purification is made new breeder reactor nuclear fuel.
What the invention has the beneficial effects as follows most economical thorium utilizes technology, wherein adopt the liquid metal catalyst carrier that heat transfer property is superb, cooling comprises the graphite fuel ball of nuclear fuel coated particle, fuel sphere is run under superelevation specific power, with the high speed of less than the 4 years phase of doubling propagation U-233 nuclear fuel.
Accompanying drawing explanation
Of the present invention above-mentioned with further feature and advantage, be described with reference to following drawings and the embodiments, wherein:
Fig. 1 is that the present invention utilizes thorium to produce the thermal neutron hypervelocity proliferating system schematic diagram of nuclear fuel.
Fig. 2 is the body schematic cross section of the ring-type multiple-unit thermal neutron hypervelocity breeder reactor of one embodiment of the invention
Fig. 3 is that the thorium that utilizes of one embodiment of the invention produces the thermal neutron hypervelocity breeder reactor of nuclear fuel and the structural representation of fission heat output system major equipment thereof.
Fig. 4 is the system flowchart of hypervelocity enrichment procedure of the present invention.
Embodiment
Refer to shown in Fig. 1, the invention provides a kind of superelevation specific power thermal neutron thorium breeder device utilizing thorium to produce nuclear fuel, comprising:
One reactor core 106, this reactor core 106 is one group of fan-shaped sheet graphite fuel ball bed, this reactor core 106 is built with containing uranium nuclear fuel graphite nodule 113, should cool by from the liquid metal catalyst carrier flowing transversely through ring-type ball bed outside to inside containing uranium nuclear fuel graphite nodule 113, uranium nuclear fuel graphite nodule 113 inside that contains in this reactor core 106 is divided into three layers: outermost layer is a graphite shells 114, secondly one deck is the mixed sintering body 115 containing uranium nuclear fuel coated particle and graphite, and interior is pure graphite nodule core 116;
One high temperature fluent metal catalyst carrier center flow channels 107, for deriving fission and the nuclear energy of reactor core production, this high temperature fluent metal catalyst carrier center flow channels 107 is positioned at the center of thermal neutron thorium proliferation device;
One low temperature liquid metal catalyst carrier decline runner 108, this decline runner is positioned at the outside of reactor core 106;
One graphite reflector 105, this graphite reflector 105 is hollow circular structure, from four sides up and down around the low temperature liquid metal catalyst carrier decline runner 108 in reactor core 106 and outside thereof;
One molten-salt breeder layer 109, within this year, molten-salt breeder layer 109 is a graphite fan blades shape hollow structure, and wherein having is cavity, is full of thoriated and melts salt as core fertilizer, this molten-salt breeder layer 109 and graphite reflector 105 cross arrangement;
One Bi-Li extractor 110, this Bi-Li extractor 110 is the extraction equipments of core fertilizer thorium and Pa-233 after irradiation, is positioned at the outside of molten-salt breeder layer 109;
One Bi-Li extractor 110 connecting tube 111, stores with the Pa-233 of out-pile the separation vessel 112 that decays and is connected, and storing Pa-233 decay in decay separation vessel 112 at Pa-233 is U-233.
The reactor core 106 of the U-233 nuclear fuel of this liquid metal cooling, in fan, its upper and lower, interior three faces are provided with graphite reflector 105, have liquid metal catalyst carrier decline runner 108 outside it, and central authorities are then high temperature fluent metal catalyst carrier rising runner 107.This molten-salt breeder layer communicates with the thoriated molten-salt breeder layer 109 of another fan blades type closed on.The reactor core of this employing liquid metal cooling nuclear fuel significantly can reduce reactor core nuclear fuel charging capacity, allows level fuel rating being increased substantially more than 30MWt/kg.
The heat transfer property of liquid metal catalyst carrier with melt compared with salt, its superiority is apparent, as shown in table 1 below.
Table 1. liquid metal catalyst carrier and the heat transfer property comparison sheet melting salt
The relational expression of based on fuel multiplication phase and its specific power is estimated: set fuel rating as p
n, fuel gain is G=CR-1, and does not consider loss and the plant load factor of fissile nuclide, then theoretic doubling time T=p
0/ (p
n* B*G) year.The fissile nuclide quality that B consumes for producing unit energy, B ≈ 0.39kg/MW*a.For solid fuel breeder reactor, also should deduct the neutron loss that sliver is captured, therefore establish CR-1 ≈ 0.05 temporarily.P is listed in table 1
nby the fuel-doubling time estimated value within the scope of 20-60MW/kg.
The theoretical doubling time of table 1.U-233 nuclear fuel and the relation of fuel rating
(fuel gain CR-1 ≈ 0.05)
| Fuel rating, MW/kg | 20 | 30 | 40 | 50 | 60 |
| Actual gain, p nBG/p 0 | 0.31 | 0.465 | 0.62 | 0.775 | 0.95 |
| Fuel-doubling time, year | 3.226 | 2.151 | 1.613 | 1.290 | 1.075 |
As seen from the above table, when fuel rating is greater than 20MW/kg, the fuel-doubling time of thermal breeder reactor quickly falls to less than 3.5 years, is far superior to the multiplication capacity of fast breeder reactor.
As a reference, the fused salt cooling graphite nodule bed power reactor heap that Berkeley National Laboratory of the U.S. has delivered, when adopting the fuel sphere of 3cm diameter, its fuel rating has arrived the level of ≈ 10MW/kg, if the liquid metal using high 16 times of thermal conductivity instead makes catalyst carrier, then its fuel rating is easy to the higher level bringing up to more than ≈ 20MW/kg naturally, and fuel rating high so technically is as seen may reach completely with liquid metal catalyst carrier at present.
The proliferative zone 109 that one thoriated fused salt is formed, it is also fan-shaped, wherein the Pa-233 that neutron produces captured by thoriated propagation salt, the half life period that transformation becomes U-233 is quite long, it is 27 hours, therefore at the arranged outside Bi-Li extractor 110 of proliferative zone, after the Pa-233 extraction in fused salt, send in the storage decay tank 112 of out-pile by pipeline 111, then the U-233 wherein generated is fluoridized separation, send into nuclear fuel and manufacture room (not shown), cause fresh fuel ball, wherein part conveying returns pebble bed reactor reactor core 106, supplements burnup wherein; Remainder can be waited until and be built new breeder reactor as first charge.
The present invention also provides a kind of method (consulting Fig. 4) of superelevation specific power thermal neutron thorium breeder fertile nuclei fuel, the method adopts aforesaid device, liquid metal is wherein adopted to cool the graphite nodule bed reactor reactor core 106 that comprises coated particle nuclear fuel, nuclear fuel is run under more than the superelevation specific power of 40MW/kg, its fuel multiplication phase reduces to less than 2 years, and the method comprises the steps;
Step one (401 of corresponding diagram 4): carry out fission reaction in a reactor core 106 using uranium as nuclear fuel, productional surplus neutron, the fissile material of loading in this uranium-bearing reactor core 106 is: the graphite nodule 113 that the coated particle fuel being core with enrichment U-235 or U-233 is formed, this reactor core 106 is made up of with the liquid metal catalyst carrier runner 107 being positioned at its center one group of fan-shaped sheet graphite fuel ball bed 106, cooling by from the liquid metal catalyst carrier flowing transversely through this reactor core 106 outside to inside containing uranium nuclear fuel graphite nodule 113 in this reactor core 106, uranium nuclear fuel graphite nodule 113 inside that contains in this reactor core 106 is divided into three layers: outermost layer is a graphite shells 114, secondly one deck is the mixed sintering body 115 containing uranium nuclear fuel coated particle and graphite, interior is pure graphite nodule core 116,
Step 2 (402 of corresponding diagram 4): in a graphite reflector 105, make the residue moderation of neutrons leaking out reactor core 106, a part returns reactor core 106, reduce its critical mass, a part is to external leakage, and the molten-salt breeder layer 109 entering thoriated fused salt produces new nuclear fuel;
Step 3 (403 of corresponding diagram 4): at one using thorium as in the molten-salt breeder layer 109 of core fertilizer, makes thorium capture neutron and produces Pa-233;
Step 4 (404 of corresponding diagram 4): the Pa-233 in the thoriated fused salt after irradiation is separated with thoriated fused salt with in Bi-Li extractor 110 by core fertilizer thorium after an irradiation;
Step 5 (405 of corresponding diagram 4): store in decay separation vessel 112 at Pa-233 and Pa-233 is decayed for U-233 and in addition Separation & Purification;
Step 6 (406 of corresponding diagram 4): in a nuclear fuel preparation facilities, the U-233 after purification is made new breeder reactor nuclear fuel.
Embodiment
Refer to Fig. 2 and Fig. 3.
Fig. 2 is the horizontal cross-section schematic diagram of the thermal neutron hypervelocity breeder reactor body of one embodiment of the invention.
This breeder reactor is combined by multiple cross one another fan reactor core 201 (in corresponding diagram 1 106) and thoriated molten-salt breeder layer 202 (in corresponding diagram 1 109).Containing the reactor core liquid metal of nuclear fuel as catalyst carrier, fuel sphere bed is flowed transversely through in the horizontal direction by the liquid metal catalyst carrier decline runner 203 (in corresponding diagram 1 108) in outer ring, absorb fission heat, temperature rises, again through porous graphite reflection horizon 205, flow into liquid metal catalyst carrier rising runner 204 (in corresponding diagram 1 107), then upwards flow out this breeder reactor.
Thoriated molten-salt breeder layer 202 is extended to the outer wall of the high temperature fluent metal catalyst carrier runner 204 (in corresponding diagram 1 107) of central authorities by the outer wall of breeder reactor, but with the thin plate of heat proof material and reactor core completely isolated, must not contact with each other with liquid metal catalyst carrier or exchange.In the outside of proliferative zone, be provided with the Bi-Li extractor 206 be connected with thoriated fused salt, the Pa-233 in thoriated fused salt is extracted, deliver to out-pile and store decay.
Fig. 3 is that the thorium that utilizes of one embodiment of the invention produces the thermal neutron hypervelocity breeder reactor of nuclear fuel and the structural representation of fission heat output system major equipment thereof, and wherein the left and right sides draws two different cross sections of the sector structure that it is alternately arranged respectively.
This thermal neutron hypervelocity proliferating system utilizing thorium to produce nuclear fuel adopts the natural secure, integral structure of full power Natural Circulation; whole reactor core and heat interchanger are all arranged on a sealing and in heat insulation container 301/321; wherein fill liquid metal catalyst carrier, liquid metal catalyst carrier liquid level is protected with the inert gas 302 a little less than atmospheric pressure.Thermofin is also equipped with in the bottom of container, as shown in 322.
Reactor core 311 (corresponding to 106 in Fig. 1 and 201 in Fig. 2) is arranged on the below of airtight container, its upper and lower and interior kerbstone by black reflection horizon 312 (in corresponding diagram 1 105 with 202 and 205 in Fig. 2) around.There is thoriated molten salt layer 312 (in corresponding diagram 1 105) outside of reactor core, makes thorium wherein absorb the neutron leaked by reactor core, generates Pa-233.
Two plate-fin primary side heat interchanger are arranged on the top of airtight container, high temperature fluent metal catalyst carrier enters one group of top-down lower resistance path 304 of both ends open by the upper header 303 (corresponding to 102 in Fig. 1) above heat interchanger, transfers heat to secondary circuit catalyst carrier (its working medium is ordered sth. separately).Secondary circuit catalyst carrier enters baffling section 309 by lower inlet pipe 306, flows through wing plate section 308 and sets out heat, then through upper end baffling section 307, then by secondary circuit catalyst carrier outlet 305 (corresponding to 101 in Fig. 1) outflow heat exchanger.
Lower collecting box 310 (corresponding to 104 in Fig. 1) is entered through heat interchanger cooled primary Ioops liquid metal catalyst carrier, gravitate flows through downtake 313 (corresponding to 108 in Fig. 1), be redistributed in all low temperature liquid metal catalyst carrier runners 314 (in corresponding diagram 2 203) around reactor core, flowing transversely through the combustion of ball bed by arrow should reactor core, upwards flowed by high temperature fluent metal catalyst carrier runner 315 (in corresponding diagram 1 104 with 204 in Fig. 2) after intensification, rising runner 317 (corresponding to 107 in Fig. 1) is entered through diffuser 316, create the driving force of Natural Circulation.
The section 318 (in corresponding diagram 2 202) of thoriated molten-salt breeder layer is drawn on the left of Fig. 3.Bi-Li extractor 319 (in corresponding diagram 2 206) is provided with in its outer rim.The Pa-233 be extracted is sent into the storage-decay tank of out-pile by delivery pipe 320 with Bi-Li extract.
Fig. 4 is the system flowchart of hypervelocity enrichment procedure of the present invention.
The system flow of hypervelocity enrichment procedure comprises the steps;
Step 401: at the breeder reactor heap in-core of a uranium-bearing-233 as nuclear fuel, make it to run under higher than the superelevation specific power of more than 20MWt/kgU-233, produce great number residue neutron;
Step 402: in a graphite reflector, make the epithermal neutron slowing down of being leaked by reactor core become thermal neutron, the latter's part returns reactor core, and participate in fission process, another part then outwards leaks in the reactor multiplication layer of thoriated fused salt;
Step 403: a thoriated fused salt reactor multiplication layer in, the residue neutron after making thorium wherein absorb slowing down produces Pa-233;
Step 404: in a Bi-Li extractor, by the Pa-233 continuous extraction that wherein generates in Bi-Li extractant, and delivers to out-pile and stores;
Step 405: store in decay separation vessel at a Pa-233, makes Pa-233 decay for U-233, and is fluoridized and purification;
Step 406: manufacture indoor at a nuclear fuel, makes new breeder reactor nuclear fuel by the U-233 after purifying.Its product major part is sent reactor core back to and is substituted the dark spentnuclear fuel of burnup, remaining volume increase part, can for building new breeder reactor.
In sum, the invention provides a kind of thermal neutron hypervelocity proliferating system utilizing thorium to produce nuclear fuel, utilize the superelevation specific power of wherein nuclear fuel, improve propagation U-233 yield, shorten the fuel multiplication phase.The core of this system is a ring-type multiple-unit thermal breeder reactor, is made up of the numerous fan-shaped reactor core of cross arrangement and proliferative zone.Its reactor core is the U-233 graphite nodule bed of liquid metal cooling, can run under superelevation specific power, produces great number residue neutron; Its proliferative zone is the liquid fused salt of thoriated, and the residue neutron that Absorbable rod fuel unit produces produces great number U-233.This thermal breeder reactor, although itself breeding ratio is lower, but the actual output rate of nuclear fuel is very high, the nuclear fuel multiplication phase significantly shortens to 1 year or shorter, complete alternative current fast neutron uranium-plutonium breeding reactor family, the thorium that utilizes making the world enter employing in advance comparatively clean is produced nuclear energy, was opened up for the second nuclear era New Times.
Also must be pointed out, except the essential characteristic of the system diagram of method and apparatus of the present invention discussed above and device exemplarily and equipment, according to the principle described in claims of the present invention and essential characteristic, utilize common engineering, various diverse ways can also be designed, device and equipment, carry out various improvement, and designs various substitute.
Above-described specific embodiment; object of the present invention, technical scheme and beneficial effect are further described; be understood that; the foregoing is only specific embodiments of the invention; be not limited to the present invention; within the spirit and principles in the present invention all, any amendment made, equivalent replacement, improvement etc., all should be included within protection scope of the present invention.
Claims (9)
1. a superelevation specific power thermal neutron thorium breeder device, comprises:
One reactor core, this reactor core is one group of fan-shaped sheet graphite fuel ball bed;
One high temperature fluent metal catalyst carrier center flow channels, for deriving fission and the nuclear energy of reactor core production, this high temperature fluent metal catalyst carrier center flow channels is positioned at the center of thermal neutron thorium proliferation device;
One low temperature liquid metal catalyst carrier decline runner, this decline runner is positioned at the outside of reactor core;
One graphite reflector, this graphite reflector is hollow circular structure, from four sides up and down around the low temperature liquid metal catalyst carrier decline runner in reactor core and outside thereof;
One molten-salt breeder layer, this molten-salt breeder layer is a graphite fan blades shape hollow structure, is full of thoriated and melts salt as core fertilizer, this molten-salt breeder layer and graphite reflector cross arrangement in cavity wherein;
One Bi-Li extractor, this Bi-Li extractor is the extraction equipment of core fertilizer thorium and Pa-233 after irradiation, is positioned at the outside of molten-salt breeder layer;
One Bi-Li extractor connecting tube, stores with the Pa-233 of out-pile the separation vessel that decays and is connected, and storing Pa-233 decay in decay separation vessel at Pa-233 is U-233.
2. superelevation specific power thermal neutron thorium breeder device as claimed in claim 1, wherein reactor core is built with containing uranium nuclear fuel graphite nodule, should cool containing uranium nuclear fuel graphite nodule by from the liquid metal catalyst carrier flowing transversely through ring-type ball bed outside to inside.
3. superelevation specific power thermal neutron thorium breeder device as claimed in claim 2, wherein the uranium nuclear fuel graphite nodule inside that contains of reactor in-core is divided into three layers: outermost layer is a graphite shells, secondly one deck is the mixed sintering body containing uranium nuclear fuel coated particle and graphite, and interior is pure graphite nodule core.
4. the method for a superelevation specific power thermal neutron thorium breeder fertile nuclei fuel, the method adopts device according to claim 1, liquid metal is wherein adopted to cool the graphite pebble bed core that comprises coated particle nuclear fuel, nuclear fuel is run under more than the superelevation specific power of 20MW/kg, its fuel multiplication phase reduces to less than 2 years, and the method comprises the steps;
Step 1: carry out fission reaction, productional surplus neutron at a reactor in-core using uranium as nuclear fuel;
Step 2: in a graphite reflector, make the residue moderation of neutrons leaking out reactor core, a part returns reactor core, reduces its critical mass, and a part is to external leakage, and the molten-salt breeder layer entering thoriated fused salt produces new nuclear fuel;
Step 3: at one using thorium as in the molten-salt breeder layer of core fertilizer, makes thorium capture neutron and produces Pa-233:
Step 4: the Pa-233 in the thoriated fused salt after irradiation is separated with thoriated fused salt with in Bi-Li extractor by core fertilizer thorium after an irradiation;
Step 5: store in decay separation vessel at Pa-233 and Pa-233 is decayed for U-233 and in addition Separation & Purification;
Step 6: in a nuclear fuel preparation facilities, the U-233 after purification is made new breeder reactor nuclear fuel.
5. the method for superelevation specific power thermal neutron thorium breeder fertile nuclei fuel as claimed in claim 4, the fissile material of wherein loading in uranium-bearing reactor core is: the graphite nodule that the coated particle fuel being core with enrichment U-235 is formed.
6. the method for superelevation specific power thermal neutron thorium breeder fertile nuclei fuel as claimed in claim 5, the fissile material that wherein uranium-bearing reactor core loads is: take U-233 as the graphite nodule that the coated particle fuel of core is formed.
7. the method for superelevation specific power thermal neutron thorium breeder fertile nuclei fuel as claimed in claim 6, wherein reactor core is made up of one group of fan-shaped sheet graphite fuel ball bed and the liquid metal catalyst carrier runner being positioned at its center.
8. the method for superelevation specific power thermal neutron thorium breeder fertile nuclei fuel as claimed in claim 7, wherein the uranium nuclear fuel graphite nodule that contains of reactor in-core cools by from the liquid metal catalyst carrier flowing transversely through this reactor core outside to inside.
9. the method for superelevation specific power thermal neutron thorium breeder fertile nuclei fuel as claimed in claim 8, wherein the uranium nuclear fuel graphite nodule inside that contains of reactor in-core is divided into three layers: outermost layer is a graphite shells, secondly one deck is the mixed sintering body containing uranium nuclear fuel coated particle and graphite, and interior is pure graphite nodule core.
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| US9786391B2 (en) | 2015-02-19 | 2017-10-10 | X-Energy, Llc | Nuclear fuel pebble and method of manufacturing the same |
| CN108198635A (en) * | 2018-02-12 | 2018-06-22 | 中国科学院上海应用物理研究所 | A kind of thorium base molten-salt breeder reactor (MSBR) reactor core |
| CN109509562A (en) * | 2018-12-07 | 2019-03-22 | 中国科学院上海应用物理研究所 | Core structure, the fuel management of fused salt pebble bed reactor and fused salt pebble bed reactor and core loading method |
| CN109509563A (en) * | 2018-11-13 | 2019-03-22 | 西安交通大学 | A kind of cooling high temperature nuclear reactor reactor core of small-sized villiaumite |
| US10522255B2 (en) | 2015-02-19 | 2019-12-31 | X-Energy, Llc | Nuclear fuel pebble and method of manufacturing the same |
| CN111540488A (en) * | 2020-05-15 | 2020-08-14 | 哈尔滨工程大学 | Flow mixing device arranged at descending section of integrated reactor pressure vessel |
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