CN110569613A - Method applied to fusion reactor cladding accurate engineering design - Google Patents
Method applied to fusion reactor cladding accurate engineering design Download PDFInfo
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- 238000005253 cladding Methods 0.000 title claims abstract description 106
- 230000004927 fusion Effects 0.000 title claims abstract description 55
- 238000013461 design Methods 0.000 title claims abstract description 49
- 238000000034 method Methods 0.000 title claims abstract description 26
- 238000004364 calculation method Methods 0.000 claims abstract description 39
- 239000000463 material Substances 0.000 claims abstract description 38
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 claims abstract description 31
- 229910052722 tritium Inorganic materials 0.000 claims abstract description 31
- 230000035755 proliferation Effects 0.000 claims abstract description 21
- 230000004907 flux Effects 0.000 claims abstract description 12
- 238000004458 analytical method Methods 0.000 claims description 10
- 230000008878 coupling Effects 0.000 claims description 8
- 238000010168 coupling process Methods 0.000 claims description 8
- 238000005859 coupling reaction Methods 0.000 claims description 8
- 230000008569 process Effects 0.000 claims description 7
- 239000002245 particle Substances 0.000 claims description 5
- 238000004088 simulation Methods 0.000 claims description 4
- 230000002457 bidirectional effect Effects 0.000 claims description 3
- 238000006243 chemical reaction Methods 0.000 claims description 3
- 239000012530 fluid Substances 0.000 claims description 3
- 230000007547 defect Effects 0.000 abstract description 2
- 239000007787 solid Substances 0.000 description 17
- 229910052734 helium Inorganic materials 0.000 description 15
- 239000001307 helium Substances 0.000 description 15
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 15
- 238000011160 research Methods 0.000 description 6
- 238000009395 breeding Methods 0.000 description 4
- 230000001488 breeding effect Effects 0.000 description 4
- JWZCKIBZGMIRSW-UHFFFAOYSA-N lead lithium Chemical compound [Li].[Pb] JWZCKIBZGMIRSW-UHFFFAOYSA-N 0.000 description 2
- 238000012443 analytical study Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002062 proliferating effect Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
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Abstract
A method applied to the accurate engineering design of the fusion reactor cladding, carry on the plasma to calculate and obtain anisotropic neutron source distribution and cladding first wall surface heat flux density distribution at first; in the physical calculation of neutron transport, anisotropic neutron source distribution obtained by plasma calculation is utilized, and material temperature distribution obtained by thermal hydraulic calculation is combined to obtain cladding inner core heat source distribution and the tritium proliferation rate of a cladding; in the thermal hydraulic calculation, the material temperature distribution of different areas in the cladding is obtained by utilizing the heat flow density distribution on the surface of the first wall of the cladding provided by plasma calculation and the nuclear heat source distribution provided by neutron transport calculation; the neutron transport calculation and the thermal hydraulic calculation need to be iterated mutually until the requirements of safe operation limit of material temperature and cladding tritium proliferation rate are met; the method can carry out engineering design on the fusion reactor cladding under the real service environment of the cladding, overcomes the defect that an isotropic neutron source and the surface heat flux density of the first wall of the uniform cladding are adopted in the traditional method, and realizes the accurate engineering design of the cladding.
Description
Technical Field
The invention relates to the technical field of fusion reactor cladding design, in particular to a method for fusion reactor cladding precise engineering design, which is a method for obtaining fusion reactor cladding engineering design parameters in a real service environment.
background
the cladding layer plays an important role in energy conversion, tritium breeding, radiation shielding and the like in the fusion reactor, wherein a coolant flows in a large number of parallel pipes to take away heat in the cladding layer, a neutron multiplier is used for increasing neutron flux so as to improve the tritium breeding ratio of the tritium breeding agent, and fuel in the reactor core of the fusion reactor is in a high-temperature (hundred million DEG C) plasma state and can have important influence on the operation condition of the cladding layer. During the operation of the plasma, a large number of neutrons and heat pulses are generated, and flow to the first wall of the cladding through radial transport, so that great challenges are brought to the design of the cladding structure in engineering, and therefore the design of the cladding structure needs to determine the structural parameters of the cladding by combining a plurality of physical fields such as plasma physics, neutron transport physics, thermal hydrodynamics and the like.
In the current design research aiming at the normal and extreme working conditions of the ITER and CFETR cladding, the surface heat flux density of the first wall of the cladding is assumed to be uniform and constant, the actual service environment of the cladding in a Tokamak device is not met, the adopted heat flux density value tends to be conservative, the design difficulty of the cladding is increased, and the detailed engineering design requirement of the fusion reactor cladding cannot be met. The first wall surface heat flow density employed in the Design study of a water-cooled solid proliferation envelope for a CFETR was a uniform 0.3MW/m as employed by Songlin Liu et al in a publication of Songlin Liu, Yong Pu, Xiaooman Cheng, et al (preceding Design of a water-cooled fiber blanket for CFETR, Fusion Engineering and Design 89(2014) 1380-1385.)2The first wall surface heat flux density employed in a Design study for CFETR helium cold solid proliferating clad in a published journal article by Hongli Chen et al (Chen HL, Li M, Lv ZL, et al. centralized Design and analysis of the same solid cooled pebble branker for CFETR, Fusion Engineering and Design 96-97 (2015) 89-94) is also uniform at 0.3MW/M2Aubert et al, overseas in a published journal article (J.Aubert, G.Aiello, N.Jonqueres, et al, Development of the water-cooled lithium lead clad for DEMO, Fusion Engineering and Design 89(2014) 1386-1391) used in analytical studies on European Fusion reactor water-cooled lithium lead clad are uniform in first wall surface heat flow density0.5MW/m2. Meanwhile, isotropic uniform neutron source assumption is adopted in the above documents, and an isotropic volume neutron source is also adopted in the neutron analysis for CFETR in a published document (zhao feng surpass, von kaifeng, cao promotion, etc., nuclear fusion and plasma physics 38(2018) 48-54).
The influence of the high-temperature plasma of the fusion reactor core on the cladding is not considered in the researches, the design and the analysis of the cladding are only carried out by adopting the assumption of simple uniform heat flux density and an isotropic neutron source, the researches are only applicable to the conceptual design stage of the cladding, the simulation of the real service environment of the fusion reactor cladding is difficult to realize, the influence of particles and heat pulses of the high-temperature plasma of the fusion reactor core on the operation of the cladding cannot be researched, and the detailed engineering design requirement of the fusion reactor cladding cannot be further met.
disclosure of Invention
in order to overcome the problems of the existing methods, the invention aims to provide a method applied to fusion reactor cladding precise engineering design based on multi-physics field coupling, so that the defect that the existing analysis design method cannot simulate the real service environment of the cladding is overcome.
The invention adopts the following technical scheme to achieve the aim:
A method applied to fusion reactor cladding precise engineering design comprises the following steps:
Step 1: according to the operation parameters of the plasma in the reactor core of the fusion reactor, a plasma transport program is adopted to construct a plasma model of the reactor core of the fusion reactor, and the anisotropic neutron source distribution and the surface heat flux density distribution of the first wall of the cladding in the reactor core of the fusion reactor are obtained through the simulation calculation of the radial transport of plasma particles and energy;
Step 2: according to the arrangement and size parameters of the initial structural material, the neutron multiplier and the tritium breeder of the fusion reactor cladding, constructing a neutron transport analysis model of the fusion reactor cladding by adopting a neutron transport program, and obtaining the nuclear heat source distribution and the tritium breeder rate of the cladding in the fusion reactor cladding by taking the anisotropic neutron source distribution obtained in the step 1 as the basis and combining the assumed material temperature distribution;
And step 3: according to the geometric structure and material components of the fusion reactor cladding, a thermodynamic and hydraulic analysis model of the fusion reactor cladding is constructed by adopting a computational fluid dynamics program, and the material temperatures of different regions in the fusion reactor cladding are obtained by combining the fusion reactor cladding inner core heat source distribution obtained in the step 2 on the basis of the cladding first wall surface heat flux density distribution obtained in the step 1;
And 4, step 4: the reaction sections of neutrons and materials in the fusion reactor cladding at different temperatures are different, so that the released heat, namely cladding inner core heat sources, are different, bidirectional coupling iteration is needed for neutron transport calculation and thermal hydraulic calculation, the neutron transport calculation provides nuclear heat source distribution for the thermal hydraulic calculation, the thermal hydraulic calculation provides different material temperature distribution for the neutron transport calculation, the neutron transport calculation and the thermal hydraulic calculation are mutually iterated, namely, the step 2 and the step 3 are alternately repeated, but the assumed material temperature distribution adopted in the primary implementation process of the step 2 needs to be adjusted to the material temperature distribution in the fusion reactor cladding obtained in the step 3 in the iteration process, and the iteration calculation is carried out until the tritium multiplication rate and the temperature distribution under the cladding structure design parameters are converged.
And 5: checking whether the tritium proliferation rate and the temperature distribution of the fusion reactor cladding obtained in the step 4 meet the requirements of material temperature limitation and tritium proliferation rate, and if the tritium proliferation rate and the temperature distribution meet the requirements of material temperature limitation and tritium proliferation rate at the same time, outputting structural design parameters of the cladding; and if the requirements of the material temperature limit and the tritium proliferation rate cannot be met simultaneously, modifying the structural design parameters of the cladding and then executing the steps 2 to 5 until the requirements of the material temperature limit and the cladding tritium proliferation rate are met.
compared with the prior art, the invention has the following advantages and innovation points:
1. The design method is based on multidisciplinary crossing, combines basic research of plasma and practical engineering application requirements of the cladding, and obtains a cladding multi-physical-field coupling design technology;
2. The design method breaks through the limitation that the influence of reactor core plasma is lacked in the existing cladding design research, and obtains the thermal safety characteristic of the cladding under the multi-field coupling condition;
3. the design method adopts multi-physics field coupling to carry out the design research of the fusion reactor cladding, and provides accurate reference for the actual operation state of the cladding.
in summary, the design method provides a fusion reactor cladding accurate engineering design method based on multi-physical field coupling of plasma, thermal hydraulic power, particle transport and the like, the obtained result is more in line with the actual operation condition of the cladding, and meanwhile, guidance can be provided for in-reactor experiment check of the fusion reactor cladding.
Drawings
FIG. 1 is a flow chart of a fusion reactor cladding precise engineering design method.
FIG. 2 is a schematic diagram of fusion reactor cladding arrangement and plasma distribution.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
According to one embodiment of the present invention, a CFETR primary helium-cooled solid-state cladding design study is performed using the process shown in FIG. 1, with the CFETR cladding arrangement and plasma profile shown in FIG. 2.
1. Establishing a CFETR reactor core plasma model by utilizing a plasma transport program such as BOUT + + and the like according to the first-stage reactor core operation design parameters of CFETR, wherein the main parameters comprise a large radius of 6.62m, a small radius of 1.79m and a central current density of 4.6MA/m2the central longitudinal field intensity is 5.77T, the fusion reactor power is 200.4MW, and the anisotropic neutron source distribution and the helium-cooled solid-state cladding first wall surface heat flux density distribution in the CFETR reactor core are obtained through CFETR reactor core plasma particles and energy radial transport simulation calculation;
2. According to the arrangement scheme and the size parameters of structural materials, neutron multipliers and tritium breeders designed by the CFETR helium cold solid cladding concept, a neutron transport program such as MCNP is utilized to build a neutron transport analysis model of the CFETR helium cold solid cladding, and the distribution of the nuclear heat source in the CFETR helium cold solid cladding and the tritium breeding rate of the cladding are obtained by combining the assumed material temperature distribution on the basis of the anisotropic neutron source distribution obtained in the step 1;
3. According to the geometric structure and material components designed by the CFETR helium cold solid state cladding concept, a computational fluid dynamics program such as Fluent and the like is adopted to construct a CFETR helium cold solid state cladding thermal hydraulic analysis model, and the material temperatures of different areas in the CFETR helium cold solid state cladding are obtained by combining the distribution of the nuclear heat sources in the CFETR helium cold solid state cladding obtained in the step 2 on the basis of the surface heat flow density distribution of the first wall of the CFETR helium cold solid state cladding obtained in the step 1;
4. And (2) bidirectional coupling iteration of neutron transport calculation and thermal hydraulic calculation, wherein MCNP neutron transport calculation provides a nuclear heat source for FLUENT thermal hydraulic calculation, FLUENT thermal hydraulic calculation provides different material temperatures for MCNP neutron transport calculation, the two are iterated mutually, and the step (2) and the step (3) are alternately repeated, but the assumed material temperature distribution adopted in the primary implementation process of the step (2) needs to be adjusted to the material temperature distribution in the CFETR helium cold solid state cladding obtained in the step (3) in the iteration process, and the iteration calculation is carried out until the tritium proliferation rate and the temperature distribution in the CFETR helium cold solid state cladding are converged under the design parameters of the cladding structure.
5. Checking whether the tritium proliferation rate and the temperature distribution of the CFETR helium cold solid state cladding obtained in the step 4 meet the requirements of material temperature limitation and tritium proliferation rate, and if the requirements of the material temperature limitation and the tritium proliferation rate are met, outputting structural design parameters of the CFETR helium cold solid state cladding; and if the requirements of the material temperature limit and the tritium proliferation rate cannot be met simultaneously, modifying the structural design parameters of the CFETR helium cold solid state cladding, and executing the steps 2 to 5 until the structural design parameters of the CFETR helium cold solid state cladding meet the requirements of the material temperature limit and the cladding tritium proliferation rate.
The above description is only an embodiment of the present invention, and is not intended to limit the scope of the present invention, and various changes may be made in the above embodiment of the present invention. All simple and equivalent changes and modifications made according to the claims and the content of the specification of the present application fall within the scope of the claims of the present patent application. The invention has not been described in detail in order to avoid obscuring the invention.
Based on the above theoretical model, the calculation flow of the invention is shown in fig. 1, and the arrangement of the fusion reactor inner cladding and the plasma distribution are shown in fig. 2.
Claims (1)
1. a method applied to fusion reactor cladding accurate engineering design is characterized in that: the method comprises the following steps:
step 1: plasma computing
According to the operation parameters of the plasma in the reactor core of the fusion reactor, a plasma transport program is adopted to construct a plasma model of the reactor core of the fusion reactor, and the anisotropic neutron source distribution and the surface heat flux density distribution of the first wall of the cladding in the reactor core of the fusion reactor are obtained through the simulation calculation of the radial transport of plasma particles and energy;
step 2: neutron transport calculation
According to the arrangement and size parameters of the initial structural material, the neutron multiplier and the tritium breeder of the fusion reactor cladding, constructing a neutron transport analysis model of the fusion reactor cladding by adopting a neutron transport program, and obtaining the nuclear heat source distribution and the tritium breeder rate of the cladding in the fusion reactor cladding by taking the anisotropic neutron source distribution obtained in the step 1 as the basis and combining the assumed material temperature distribution;
and step 3: thermodynamic hydraulic calculation
according to the geometric structure and material components of the fusion reactor cladding, a thermodynamic and hydraulic analysis model of the fusion reactor cladding is constructed by adopting a computational fluid dynamics program, and the material temperatures of different regions in the fusion reactor cladding are obtained by combining the fusion reactor cladding inner core heat source distribution obtained in the step 2 on the basis of the cladding first wall surface heat flux density distribution obtained in the step 1;
And 4, step 4: coupled iterative computation
The reaction sections of neutrons and materials in the fusion reactor cladding at different temperatures are different, so that the released heat, namely cladding inner core heat sources, are different, bidirectional coupling iteration is needed for neutron transport calculation and thermal hydraulic calculation, the neutron transport calculation provides nuclear heat source distribution for the thermal hydraulic calculation, the thermal hydraulic calculation provides different material temperature distribution for the neutron transport calculation, the neutron transport calculation and the thermal hydraulic calculation are mutually iterated, namely, the step 2 and the step 3 are alternately repeated, but the assumed material temperature distribution adopted in the primary implementation process of the step 2 needs to be adjusted to the material temperature distribution in the fusion reactor cladding obtained in the step 3 in the iteration process, and the iteration calculation is carried out until the tritium multiplication rate and the temperature distribution under the cladding structure design parameters are converged.
And 5: determining whether or not the design requirement is satisfied
checking whether the tritium proliferation rate and the temperature distribution of the fusion reactor cladding obtained in the step 4 meet the requirements of material temperature limitation and tritium proliferation rate, and if the tritium proliferation rate and the temperature distribution meet the requirements of material temperature limitation and tritium proliferation rate at the same time, outputting structural design parameters of the cladding; and if the requirements of the material temperature limit and the tritium proliferation rate cannot be met simultaneously, modifying the structural design parameters of the cladding and then executing the steps 2 to 5 until the requirements of the material temperature limit and the cladding tritium proliferation rate are met.
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| CN118427905A (en) * | 2024-06-26 | 2024-08-02 | 中国科学院合肥物质科学研究院 | Rapid calculation method suitable for fusion reactor cladding first wall heat-tritium coupling transport |
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