CN103886918B - Utilize hybrid reactor system and the operation method of water-cooled thorium-uranium fuel module arranged crosswise - Google Patents
Utilize hybrid reactor system and the operation method of water-cooled thorium-uranium fuel module arranged crosswise Download PDFInfo
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Abstract
The invention belongs to Fusion-fission energy mix heap and blanket design field, particularly to a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise and operation method.The present invention is alternately arranged by the hoop optimization of natural thorium fuel reaction module and natural uranium fuel reaction module, make full use of seed-covering strategy to improve the neutron economy that system is overall, realize making full use of the target of thorium fuel under higher-energy amplification, namely utilize the good Neutron properties of water-cooled natural uranium module to make up natural thorium neutron multiplication and the deficiency of energy amplification, the energy of system amplifies and neutron multiplication relies primarily on natural uranium, and the unnecessary neutron produced from natural uranium is for driving the operation of natural thorium and breeding233U.When in natural thorium233When U runs up to a certain amount of, progressively natural uranium can be taken out and replace with new natural thorium, and can finally realize the full thorium fuel of hybrid reactor, the operation of thorium, uranium circulation.
Description
Technical field
The invention belongs to Fusion-fission energy mix heap and blanket design field, particularly to a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise and operation method.
Background technology
On the current earth, explored thorium reserves are about 3 times of uranium reserve, and being bred by advanced reactor or change will232Th converts to233U, will be greatly enhanced the storage capacity of existing nuclear fuel resources.Nuclear energy circle proposes the idea utilizing fusion-fission hybrid reactor to carry out fertile nuclei fuel in late 1960s, namely outside fusion facility, depleted uranium, natural uranium or natural thorium fuel are loaded as proliferative zone, utilize the high-energy neutron that fusion reaction produces at proliferative zone internal breeding nuclear fuel, and carry out production capacity output, fuel after propagation is available for thermal-neutron reactor and uses, and this technology is to solve nuclear power development center fuel crunch and utilize a kind of effective means of fusion energy in advance.
Use in hybrid reactor on thorium fuel both at home and abroad and carried out many research work, as above century 70 masschusetts, u.s.a science and engineering proposes to adopt the thorio fused salt scheme of the suppressed fission easy fission fuel conversion ratio of raising, and Turkey Nigde and Gazi university use solid thorium fuel to breed in ARIES-RS fusion reactor233The scheme of U, the hybrid reactor thorium-uranium fuel circulating research that Osaka, Japan university carries out, and in the recent period Texas ,Usa university fusion research center devise scheme that a kind of hybrid reactor is combined with presurized water reactor to utilize thorium fuel, by thorium fuel in hybrid reactor internal breeding,233The accumulation of U content is inserted presurized water reactor when reaching certain enrichment and is burnt.At home, from the eighties start Chinese Academy of Sciences's plasma with southwest physical study institute devise the experiment hybrid reactor TETB, TETB-II, the FEB that are target with fertile nuclei fuel successively.In the recent period under the support that International Thermal-Nuclear Experimental Reactor (ITER) plan is special, domestic many units carried out with production capacity be main target subcritical energy pile physical Design and the research of experimental check, wherein Tsing-Hua University assume responsibility for the research topic containing the subcritical energy pile design of thorium fuel.
The key issue that the subcritical blanket design of thoriated faces is: for232Th fuel, the threshold energy of its fission reaction is up to 1MeV, and thermal neutron absorption cross section is close2383 times of U, namely232The neutron multiplication ability of Th is very weak, and neutron economy is poor.Several thorio hybrid reactors above-mentioned research shows that the energy amplification M of pure Th base hybrid reactor propagation covering is relatively low, about 2, will realize production capacity output, it is achieved the early stage application of fusion energy, Fusion power will propose bigger challenge.For conventional critical pile, for efficient realization232The use of Th fuel, can adopt higher enrichment nuclear fuel (235U or239Pu), obtain the lifting of overall neutron economy, start the operation of whole reactor.For hybrid reactor, being then need to realize when natural abundance degree fuel starting, meet system production capacity, tritium is bred and fuel breeding.
Summary of the invention
The present invention is for overcoming the deficiencies in the prior art, propose to utilize hybrid reactor system and the operation method of water-cooled thorium-uranium fuel module arranged crosswise, the program can only use natural uranium and natural thorium fuel, it is achieved under the premise of higher-energy amplification, efficiently utilizes thorium fuel and ensures that tritium is controlled oneself.And can realize in heap233The utilization of U, it is achieved thorium, uranium fuel circulation in heap.
A kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise, described hybrid reactor system is annular cladding structure, described annular cladding structure is connected by multiple reaction modules and constitutes, in each described reaction module from inside to outside, setting gradually fuel region, Chan Chuan district and blind zone and be sequentially connected, wherein said each fuel region is the loop configuration constituted that is connected by the multiple fuel modules on the direction being perpendicular to described hybrid reactor system planar annular；In described hybrid reactor system, each fuel region is connected with adjacent fuel region respectively constitutes system fuel district, in described system fuel district, plasma slab is set, described each Chan Chuan district is connected with adjacent Chan Chuan district respectively and constitutes Chan Chuan district, and described each blind zone is connected with adjacent blind zone respectively and constitutes system mask district；
Described each fuel region is spaced to be connected with multiple coolant layer by multiple fuel beds and constitutes, and wherein innermost layer arranges the 1 grate firing bed of material, and outermost layer arranges 1 layer of coolant layer；Described each Chan Chuan district is spaced to be connected with multiple product tritium material layers by multiple coolant layer respectively and constitutes, wherein innermost layer and outermost layer are respectively provided with 1 layer and produce tritium material layer, the outermost layer coolant layer of described each fuel region is produced tritium material layer with the innermost layer in corresponding Chan Chuan district respectively and is connected, and the outermost layer in described each Chan Chuan district produces tritium material layer and is connected with corresponding blind zone.
All fuel beds in described single reaction module are natural uranium or natural thorium.
The coolant that described coolant layer uses is light water.
The product tritium material that described product tritium material layer uses is Li4SiO4。
The operation method of a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise, utilizes the good Neutron properties of water-cooled natural uranium to make up natural thorium neutron multiplication and the deficiency of energy amplification, and concrete scheme is as follows:
Having at least all fuel beds in 1 reaction module in described hybrid reactor system is natural thorium, and all fuel beds in remaining reaction module are natural uranium；The energy output of described hybrid reactor system initial operating stage and neutron multiplication rely on natural uranium, and the extra neutrons of generation are used for driving thorium module to carry out233U fuel breeding；Along with hybrid reactor system is run, in natural thorium233U fuel accumulates gradually, and the share of system capacity contribution is strengthened by it, when in natural thorium233When U runs up to predetermined amount, successively natural uranium is taken out, replacing with new natural thorium, until all having replaced, finally realizing the full thorium fuel of hybrid reactor system, thorium, uranium fuel circular flow；
When being provided with more than 2 natural thorium fuel reaction modules before described hybrid reactor system is run, natural thorium fuel reaction module and natural uranium fuel reaction module uniform crossover need to be made arranged evenly.
The coolant that described coolant layer uses is light water.
The product tritium material that described product tritium material layer uses is Li4SiO4。
The core concept of the present invention: consider that water-cooled natural uranium system has good energy under mixing power spectrum and amplifies and neutron multiplication ability, water-cooled natural uranium hybrid reactor can reach the energy amplification of 15 to 20, this characteristic can be made full use of in the design for this, design natural uranium fuel reaction module two kinds independent and natural thorium fuel reaction module, fuel region, Chan Chuan district and blind zone arrangement is all adopted in module.Unite in the mid-a part of space feedwater right uranium series of cold day that reserves of hybrid reactor system, thorium-uranium fuel arranged crosswise is carried out in the hoop direction of hybrid reactor system, the energy output of initial operating stage and neutron multiplication rely primarily on natural uranium, and the extra neutrons of generation may be used for driving natural thorium to carry out233U fuel breeding.This space is arranged and is advantageous in that, inserting of natural thorium fuel reaction module does not break the neutronics environment that water-cooled natural uranium system itself is good, the Neutron properties of natural uranium fuel reaction module is limited only by its material and geometrical property constraint positive definite, its energy high under mixing power spectrum amplifies and neutron multiplication ability is retained, system obtains preferably overall neutron economy: hybrid reactor system is while maximizing available neutron, reasonably in each main nuclear reaction determining its performance, such as fission reaction, produce tritium reaction and fuel breeding reaction, be allocated.Thus fuel breeding, achieves a good balance between energy output and tritium propagation target.Natural uranium fuel reaction module is as the seed of one drive ignition of system initial stage, it is achieved the startup of hybrid reactor system.Simultaneously along with operation, in natural thorium233U fuel accumulates gradually, and the share of system capacity contribution is gradually increased by it, now can be taken out by natural uranium gradually, replace with new natural thorium, be finally transitioned into full thorium fuel, it is achieved thorium, uranium fuel circular flow.
The present invention utilizes fuel module covering arranged crosswise strategy, realize in hybrid reactor system, efficiently utilize thorium fuel the higher energy amplification of maintenance, being alternately arranged of optimization is realized at the hoop of hybrid reactor system by natural thorium fuel reaction module and natural uranium fuel reaction module, calculating simulation chooses the volume share of suitable natural thorium fuel reaction module, this technology utilizes seed-covering strategy to improve the neutron economy that system is overall, realize making full use of the target of natural thorium fuel under higher-energy amplification, namely utilize the good Neutron properties of water-cooled natural uranium system to make up natural thorium neutron multiplication and the deficiency of energy amplification, the energy of system amplifies and neutron multiplication relies primarily on natural uranium, the unnecessary neutron produced from natural uranium is for driving the operation of natural thorium and breeding233U.When in natural thorium233When U content runs up to a certain amount of, progressively natural uranium can be taken out and replace with new natural thorium, and can finally realize the full thorium fuel of hybrid reactor, thorium, uranium circular flow.
Described natural uranium fuel reaction module and natural thorium fuel reaction module are radially all comprising fuel region, Chan Chuan district and blind zone successively, fuel region and Chan Chuan district light water cool down, fuel region realizes production capacity and fuel breeding function, and Chan Chuan district utilizes the neutron that fuel region leaks out to realize tritium propagation.
Described natural uranium fuel reaction module, when water-cooled, choose suitable fuel moderator volume ratio, utilize the Neutron properties that water-cooled natural uranium system is good under mixing power spectrum, during the initial launch of hybrid reactor system, mainly undertake energy amplify and neutron multiplication function.
Described natural uranium module and natural thorium module at the loading strategy of the hoop direction arranged crosswise of hybrid reactor system,233U fuel breeding is bred spatially realization with system production capacity and tritium and is separated, and optimizes neutron multiplication and utilizes process, improving the overall neutron economy of hybrid reactor system.
Described natural thorium fuel reaction module is along with the operation of hybrid reactor, in it233U constantly accumulates, and the energy of system is amplified contribution and is gradually increased by it, it is possible to progressively being replaced with new natural thorium by natural uranium, now the production capacity of hybrid reactor is mainly by burning233U realizes.
The invention have the benefit that
(1) the thorium-uranium fuel module arranged crosswise covering scheme of the present invention is under the premise ensureing production capacity output and tritium propagation performance, it is possible to makes full use of natural thorium and carries out233U fuel breeding, it is possible to support optional wider range of volume share of natural thorium, there is wider running space, it is possible to be adjusted according to operational objective, reach as high as 60%；
(2) the hybrid reactor system invented achieves that startup merely with natural uranium and natural thorium, and there is the utilization rate of significantly high fuel, this will be greatly enhanced the storage capacity of existing nuclear fuel resources, by international cooperative programs, within 2035, likely reach the Science and Technology target that the feasibility of 500MW Fusion power heap is built in checking；The fusion reactor of ITER scale is realized efficient thorium-uranium circulation as persistent erection of the penis component in its fusion covering；Fusion-fission hybrid reactor will be that a kind of tool grows a lot the new technique effectively utilizing thorium resources in space；
(3) in the natural thorium fuel module of the present invention233U breeds superior performance, along with the share of power output contribution is strengthened by it, progressively can replace natural uranium fuel module with new natural thorium fuel module, it is achieved in heap233U burns, full thorium fuel, thorium, uranium circular flow.
Accompanying drawing explanation
Fig. 1 is the hybrid reactor system annular plate-like cladding structure schematic diagram of the embodiment of the present invention 1, adopts one-dimensional " D " the font model simplified to simulate cladding structure；Wherein Fig. 1 a is for simplifying one-dimensional " D " font covering model structural representation, and Fig. 1 b is covering partial enlargement design sketch；
Number in the figure: I-fuel region；II-Chan Chuan district；III-blind zone；1-fuel bed；2-coolant layer；3-produces tritium material layer；4-screen layer.
Fig. 2 is the embodiment of the present invention 1 hybrid reactor system thorium-uranium fuel module covering hoop and pole to the schematic diagram of arranged crosswise；Wherein Fig. 2 a is covering hoop fuel module arranged crosswise (equatorial plane) structural representation, and Fig. 2 b is covering pole to fuel module crossed configuration schematic diagram；
Wherein: U represents natural uranium fuel reaction module；Th represents natural thorium fuel reaction module；IV represents divertor.
Detailed description of the invention
The invention provides a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise and operation method, below in conjunction with the drawings and specific embodiments, the present invention will be further described.
A kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise, described hybrid reactor system is annular cladding structure, described annular cladding structure is connected by multiple reaction modules and constitutes, in each described reaction module from inside to outside, setting gradually fuel region I, Chan Chuan district II and blind zone III and be sequentially connected, wherein said each fuel region I is the loop configuration constituted that is connected by the multiple fuel modules on the direction being perpendicular to described hybrid reactor system planar annular；In described hybrid reactor system, each fuel region I is connected with adjacent fuel region I respectively constitutes system fuel district, in described system fuel district, plasma slab is set, described each Chan Chuan district II is connected with adjacent Chan Chuan district II respectively and constitutes Chan Chuan district, and described each blind zone III is connected with adjacent blind zone III respectively and constitutes system mask district；
Described each fuel region I is spaced to be connected with multiple coolant layer 2 by multiple fuel beds 1 and constitutes, and wherein innermost layer arranges the 1 grate firing bed of material 1, and outermost layer arranges 1 layer of coolant layer 2；Described each Chan Chuan district II is spaced to be connected with multiple product tritium material layers 3 by multiple coolant layer 2 respectively and constitutes, wherein innermost layer and outermost layer are respectively provided with 1 layer and produce tritium material layer 3, the outermost layer coolant layer 2 of described each fuel region I is produced tritium material layer 3 respectively and is connected with the innermost layer of corresponding Chan Chuan district II, and the outermost layer of described each Chan Chuan district II produces tritium material layer 3 and is connected with corresponding blind zone III.
All fuel beds 2 in described single reaction module are natural uranium or natural thorium.
The coolant that described coolant layer 2 uses is light water.
The product tritium material that described product tritium material layer 3 uses is Li4SiO4。
The operation method of a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise, utilizes the good Neutron properties of water-cooled natural uranium to make up natural thorium neutron multiplication and the deficiency of energy amplification, and concrete scheme is as follows:
Having at least all fuel beds 1 in 1 reaction module in described hybrid reactor system is natural thorium, and all fuel beds 1 in remaining reaction module are natural uranium；The energy output of described hybrid reactor system initial operating stage and neutron multiplication rely on natural uranium, and the extra neutrons of generation are used for driving thorium module to carry out233U fuel breeding；Along with hybrid reactor system is run, in natural thorium233U fuel accumulates gradually, and the share of system capacity contribution is strengthened by it, when in natural thorium233When U runs up to predetermined amount, successively natural uranium is taken out, replacing with new natural thorium, until all having replaced, finally realizing the full thorium fuel of hybrid reactor system, thorium, uranium fuel circular flow；
When being provided with more than 2 natural thorium fuel reaction modules before described hybrid reactor system is run, natural thorium fuel reaction module and natural uranium fuel reaction module uniform crossover need to be made arranged evenly.
The coolant that described coolant layer 2 uses is light water.
The product tritium material that described product tritium material layer 3 uses is Li4SiO4。
Embodiment 1
This hybrid reactor system is made up of Liang great district, i.e. natural uranium fuel reaction module district and natural thorium fuel reaction block region, natural uranium fuel reaction module and natural thorium fuel reaction module are alternately arranged in the hoop direction of hybrid reactor, it is possible to select two kinds of fuel reaction modules in hoop each shared volume share ratio according to the operational objective of system.The initial stage natural uranium fuel reaction module run in system, as starting seed, plays production capacity output and the effect of neutron multiplication, and the extra neutrons of generation are used for driving natural thorium district to breed233U.Natural uranium fuel reaction module and natural thorium fuel reaction module all include three regions, and namely fuel region I, Chan Chuan district II and blind zone III, fuel region I and Chan Chuan district II adopt light water as coolant and moderator.
As depicted in figs. 1 and 2, the method is specifically implemented by the following steps:
(1) the natural uranium fuel reaction module described in is by San great Qu: water-cooled tabular natural uranium fuel district I, water-cooled Li4SiO4Chan Chuan district II and blind zone III is constituted, wherein fuel region I primarily serves the effect of system capacity amplification and neutron multiplication, it is mounted with the natural uranium fuel block that 5 pieces of thickness is 2cm, By Fusion Neutron is by the water institute slowing down of fuel region, the mixed spectrum that a fast thermography combines is formed, in natural uranium in whole module235U absorb thermal neutron and238U absorbs fast neutron and fissions, and releases energy and extra neutron, part be leaked in Chan Chuan the district in and6Li occurs to produce tritium reaction propagation tritium, as the fuel of fusion reactor plasma slab.Blind zone stops neutron to enter the superconducting coil of outside, plays protective action.Natural uranium fuel reaction module, by selecting the loading ratio of fuel region I fuel and moderator to regulate the neutron energy spectrum of natural uranium module, optimizes the energy amplification of natural uranium fuel reaction module, easy fission fuel conversion ratio and product tritium rate.Entering the water-cooled natural uranium system after optimizing, the volume ratio choosing fuel and moderator is 2.0, and its amplification of hybrid reactor that complete natural uranium loads reaches 18.0, produces tritium rate and reaches 1.35.The extra neutrons that natural uranium fuel district I produces can also be leaked to the natural thorium fuel module fuel region I being adjacent and carry out fuel breeding and Chan Chuan district II carries out producing tritium.
(2) the natural thorium fuel reaction module described in is adjacent at hoop with natural uranium fuel reaction module, is also made up of three great Qu: water-cooled tabular natural thorium fuel region I, water-cooled Li4SiO4Chan Chuan district II and blind zone III is constituted, wherein fuel region I plays the effect of breed fuel at the initial stage that system is run mainly through absorption neutron, it is mounted with the natural thorium fuel slug that 4 pieces of thickness is 2cm, By Fusion Neutron is by the water institute slowing down of fuel region I, the mixed spectrum that a fast thermography combines is formed, in natural thorium in whole module232Th absorbs thermal neutron and transfers to233U, and a small amount of fast fission can be occurred to carry out production capacity with fast neutron, part be leaked in Chan Chuan the district in and6Li occurs to produce tritium reaction propagation tritium, as the fuel of fusion reactor plasma slab.Blind zone III stops neutron to enter the superconducting coil of outside, plays protective action.Along with the operation of hybrid reactor system, accumulation in natural thorium fuel region I233U nucleic improves constantly,233U absorbs thermal neutron and fissions, and the productivity contribution of system can be gradually stepped up by thorium module, and its product tritium amount improves constantly simultaneously.
(3) the natural uranium fuel reaction module described in and the scheme of natural thorium fuel reaction module covering arranged crosswise, mainly carry out in hoop direction, namely adopt identical nuclear fuel, respectively natural uranium or natural thorium fuel to direction in pole.The volume share of hoop natural thorium fuel reaction module depends primarily on the operational objective of system, and namely production capacity, tritium are controlled oneself and stressed with the relative of fuel breeding ability.The volume share of natural thorium fuel is more high, system233U multiplication capacity is more strong, but the energy amplification of system and product tritium rate are more low, and vice versa.In the design of energy mix heap, the thermal power of 3000MW to be realized, it is contemplated that ITER loads the Fusion power restriction of 500MW, energy amplification needs more than 6, and produce tritium rate need to more than 1.05, under this two constraints, maximum supported thorium fuel volume share is 60%.
(4) the hybrid reactor scheme described in, along with the operation of system, the easy fission fuel of accumulation in natural thorium fuel region I233U is on the increase, the production capacity of natural thorium fuel reaction module and product tritium ability step up, product tritium and production capacity share to whole system also step up, when meeting system operational objective, gradually natural uranium in natural uranium fuel reaction module can be taken out, replacing with new natural thorium, now the natural thorium fuel reaction module after propagation undertakes production capacity and the neutron multiplication function of system gradually as seed zone, by accumulation in it233U burns, and drives new natural thorium breed fuel, is thus transitioned into the hybrid reactor system of full thorium fuel reaction module gradually completely, it is achieved thorium-uranium fuel circulates.
Claims (6)
1. the hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise, it is characterized in that: described hybrid reactor system is annular cladding structure, described annular cladding structure is connected by multiple reaction modules and constitutes, in each described reaction module from inside to outside, setting gradually fuel region (I), Chan Chuan district (II) and blind zone (III) and be sequentially connected, wherein said each fuel region (I) is the loop configuration constituted that is connected by the multiple fuel modules on the direction being perpendicular to described hybrid reactor system planar annular；In described hybrid reactor system, each fuel region (I) is connected with adjacent fuel region (I) respectively constitutes system fuel district, in described system fuel district, plasma slab is set, described each Chan Chuan district (II) is connected with adjacent Chan Chuan district (II) respectively and constitutes Chan Chuan district, and described each blind zone (III) is connected with adjacent blind zone (III) respectively and constitutes system mask district；
Described each fuel region (I) is spaced to be connected with multiple coolant layer (2) by multiple fuel beds (1) and constitutes, wherein innermost layer arranges the 1 grate firing bed of material (1), and outermost layer arranges 1 layer of coolant layer (2)；Described each Chan Chuan district (II) is spaced to be connected with multiple products tritium material layer (3) by multiple coolant layer (2) respectively and constitutes, wherein innermost layer and outermost layer are respectively provided with 1 layer and produce tritium material layer (3), the outermost layer coolant layer (2) of described each fuel region (I) is produced tritium material layer (3) with the innermost layer in corresponding Chan Chuan district (II) respectively and is connected, and the outermost layer of described each Chan Chuan district (II) produces tritium material layer (3) and is connected with corresponding blind zone (III)；
All fuel beds (1) in single described reaction module are natural uranium or are natural thorium；At least a part of which has all fuel beds (1) in 1 reaction module to be natural thorium, and all fuel beds (1) in remaining reaction module are natural uranium；The energy output of described hybrid reactor system initial operating stage and neutron multiplication rely on natural uranium, and the extra neutrons of generation are used for driving thorium module to carry out233U fuel breeding；Along with hybrid reactor system is run, in natural thorium233U fuel accumulates gradually, and the share of system capacity contribution is strengthened by it, when in natural thorium233When U runs up to predetermined amount, successively natural uranium is taken out, replacing with new natural thorium, until all having replaced, finally realizing the full thorium fuel of hybrid reactor system, thorium, uranium fuel circular flow；
When being provided with more than 2 natural thorium fuel reaction modules before described hybrid reactor system is run, natural thorium fuel reaction module and natural uranium fuel reaction module uniform crossover need to be made arranged evenly.
2. a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise according to claim 1, it is characterised in that: the coolant that described coolant layer (2) uses is light water.
3. a kind of hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise according to claim 1, it is characterised in that: the product tritium material that described product tritium material layer (3) uses is Li4SiO4。
4. the operation method of the hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise as claimed in claim 1, it is characterized in that, utilizing the good Neutron properties of water-cooled natural uranium to make up natural thorium neutron multiplication and the deficiency of energy amplification, concrete scheme is as follows:
Having at least all fuel beds (1) in 1 reaction module in described hybrid reactor system is natural thorium, and all fuel beds (1) in remaining reaction module are natural uranium；The energy output of described hybrid reactor system initial operating stage and neutron multiplication rely on natural uranium, and the extra neutrons of generation are used for driving thorium module to carry out233U fuel breeding；Along with hybrid reactor system is run, in natural thorium233U fuel accumulates gradually, and the share of system capacity contribution is strengthened by it, when in natural thorium233When U runs up to predetermined amount, successively natural uranium is taken out, replacing with new natural thorium, until all having replaced, finally realizing the full thorium fuel of hybrid reactor system, thorium, uranium fuel circular flow；
When being provided with more than 2 natural thorium fuel reaction modules before described hybrid reactor system is run, natural thorium fuel reaction module and natural uranium fuel reaction module uniform crossover need to be made arranged evenly.
5. the operation method of the hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise according to claim 4, it is characterised in that: the coolant that described coolant layer (2) uses is light water.
6. the operation method of the hybrid reactor system utilizing water-cooled thorium-uranium fuel module arranged crosswise according to claim 4, it is characterised in that: the product tritium material that described product tritium material layer (3) uses is Li4SiO4。
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