Helium-cooled fusion cladding experimental module device

Abstract

The invention discloses a helium cold fusion cladding experiment module device, which mainly comprises a first wall proliferation agent area and a rear baffle plate, is circumferentially provided with a cover plate, a bottom plate, a left side plate and a right side plate, has higher engineering characteristics similar to a cladding design scheme, is convenient to carry out neutronics measurement, and is high in reliability. Based on the device, the technical level of fusion blanket neutronics verification and measurement technology and blanket tritium breeding performance evaluation in China can be improved, independent tritium production blanket performance data is accumulated, the requirement of ITER-TBM engineering development is met, and a foundation is laid for CFETR helium cooling blanket engineering design.

Description

Technical Field

[0001] The invention relates to the technical field of fusion energy, and in particular to a helium-cooled fusion blanket experimental module device. Background Art

[0002] The tritium breeding ratio (TBR) of the fusion blanket is an important parameter to prove the tritium "self-sustaining" of the fusion reactor. Its design value is affected by nuclear data, neutron simulation methods and engineering factors. The high-precision evaluation of TBR includes the quantification of design uncertainty and the verification of design accuracy, which requires the neutron integration experiment of the tritium blanket scaled-down module as a benchmark.

[0003] With the deepening of the research on ITER TBM and fusion DEMO reactor, each ITER member country has proposed its own fusion blanket design scheme, based on which a small number of simulation devices have been built and neutron experiments have been carried out. Japan has built a solid breeder blanket module containing a simulated water-cooled blanket of F82H / Li2TiO3 (40% 6Li) / Be structure, and carried out neutron experiments of single-layer / double-layer / triple-layer breeder modules. The results show that the tritium production rate is well consistent with the calculation and experiment in the absence of a reflective layer, but the calculated value is overestimated to 10% for the case of a reflective layer and multiple layers. The European Union has established a helium-cooled ball bed blanket experimental module (HCPB) and a helium-cooled lithium-lead blanket module (HCLL) to verify its design basis. The HCPB experiment shows that the calculated value is underestimated by about 10% on average, and the HCLL calculated value is in good agreement with the experimental value. India has carried out neutron experiments on lead-lithium cold ceramic blankets composed of Li2 TiO3 ceramic spheres and lead using a DT neutron tube, and the uncertainty of tritium production measurement is 8.3%. These experiments partially verified the blanket design of ITER TBM and DEMO, but the structures of these blanket experimental modules are generally simple and simplified, which cannot reflect the real engineering characteristics of the blanket. The accuracy of the tritium production rate and activation reaction rate obtained in the experiment needs to be further improved.

[0004] In terms of the evaluation of the tritium breeding performance of the blanket based on neutron experiments, Youssef MZ et al. systematically evaluated the prediction uncertainty of the tritium production rate based on the results of the USDOE / JAERI series of experiments, and extrapolated it to the total tritium breeding ratio of the test assembly and the blanket design safety factor. This result can only be used for the Li2O breeder blanket, but its method can guide other blankets. Researchers from institutions such as ENEA in Italy and KIT in Germany conducted a sensitivity analysis of the tritium breeding rate based on the results of HCPB and HCLL experiments. The results showed that the total uncertainty of the calculated value itself was 8-10%. Due to the lack of high-precision neutron experiments, a systematic evaluation of the tritium breeding performance of the current ceramic breeder pebble bed blanket has not been carried out.

[0005] At present, the tritium breeding performance of fusion blanket in China is all based on simulation results, and there are no literature related to blanket neutronics experiments with engineering characteristics and related tritium breeding performance evaluation. Summary of the invention

[0006] In view of this, an object of the present invention is to provide a helium-cooled fusion blanket experimental module device.

[0007] The present invention provides a helium-cooled fusion blanket experimental module device, characterized in that the module device is provided with a first wall containing tungsten armor, a breeder region and a rear baffle in sequence along the radial direction, and the module device is provided with a cover plate, a bottom plate, a left side plate and a right side plate along the circumferential direction, and the breeder region includes a cavity formed by the first wall, the rear baffle, the cover plate, the bottom plate, the left side plate and the right side plate;

[0008] The multiplier zones are arranged radially from the first wall to the rear baffle in sequence with multiple multiplier zones of different sizes from small to large, neutron multiplying materials are arranged between the multiplier zones, and cooling baffles are arranged between the multiplier zones and the neutron multiplying materials.

[0009] Furthermore, the thickness of the tungsten armor is no more than 2 mm.

[0010] Furthermore, the breeding agent area and the cooling baffle are provided with cooling channels, and the rear baffle and the cover plate are provided with tritium extraction channels.

[0011] Furthermore, the number of proliferation agent zones is 5.

[0012] Furthermore, a value-added agent container assembly is arranged in the upper middle part of the proliferation agent zone, and a proliferation agent is arranged in the region of the proliferation agent zone except for the value-added agent container assembly. The proliferation agent is lithium orthosilicate, and the lithium orthosilicate has a ball bed structure, and the diameter of the small balls is 0.8-1.2 mm.

[0013] Furthermore, the value-added agent container assembly includes a value-added agent container and a plug. The value-added agent container is provided with plugs arranged in sequence along the axial direction, and the plugs are provided with detection pieces inside.

[0014] Furthermore, the neutron multiplication material is beryllium, the beryllium is a pebble bed structure, and the pebble bed diameter is 0.5-1.5 mm.

[0015] Furthermore, the cooling baffle material is low-activation steel CLF-1.

[0016] Furthermore, the first wall, the rear baffle, the cover plate, the bottom plate, the left side plate and the right side plate are made of low-activated steel CLF-1.

[0017] The principle and beneficial effects of the present invention are as follows: the helium-cooled fusion blanket experimental module device of the present invention has high engineering characteristics similar to the blanket design scheme, and is convenient for neutronic measurement. Based on the device, the technical level of fusion blanket neutronic verification, measurement technology and blanket tritium proliferation performance evaluation in my country can be improved, and independent tritium-producing blanket performance data can be accumulated to meet the needs of ITER-TBM project development and lay the foundation for CFETR helium-cooled blanket engineering design. BRIEF DESCRIPTION OF THE DRAWINGS

[0018] Figure 1 It is a side view of the helium-cooled fusion blanket experimental module device in Example 1 of the present invention;

[0019] Figure 2 This is a bottom view of the helium-cooled fusion blanket experimental module device in Example 1 of the present invention;

[0020] Figure 3 It is a top view of the helium-cooled fusion blanket experimental module device in Example 1 of the present invention;

[0021] Figure 4 This is a schematic diagram of the structure of the value-added agent container assembly in Example 1 of the present invention.

[0022] 1. First wall, 2. Back baffle, 3. Cover plate, 4. Bottom plate, 5. Left side plate, 6. Right side plate, 7. Proliferator area, 8. Neutron multiplication material, 9. Cooling baffle, 10. Proliferator, 71. Proliferator container, 72. Plug, 73. Block, 74. Detection piece. DETAILED DESCRIPTION

[0023] Example 1

[0024] The helium-cooled fusion blanket experimental module device of the present invention is a helium-cooled ball bed blanket design scheme based on magnetic confinement fusion CFETR, and the blanket design scheme adopts a flat-plate breeding zone, wherein the blanket module is composed of a first wall and tungsten armor, a cover plate, a rear baffle, a cover plate, a bottom plate, a left plate and a right plate, etc. The blanket module uses 12MPa helium as a coolant, a ceramic lithium silicate ball bed as a tritium breeder, metal beryllium as a neutron multiplier, and low-activation steel as a structural material.

[0025] Specifically, the present invention provides a helium-cooled fusion blanket experimental module device, characterized in that the module device is sequentially provided with a first wall 1 containing tungsten armor, a breeder region and a rear baffle 2 in radial direction, and the module device is circumferentially provided with a cover plate 3, a bottom plate 4, a left side plate 5 and a right side plate 6, and the breeder region includes a cavity formed by the first wall 1, the rear baffle 2, the cover plate 3, the bottom plate 4, the left side plate 5 and the right side plate 6;

[0026] The breeder area is radially arranged from the first wall 1 to the rear baffle 2 with multiple breeder areas 7 of different sizes arranged in sequence from small to large. Neutron multiplication materials 8 are arranged between the breeder areas 7, and cooling baffles 9 are arranged between the breeder areas 7 and the neutron multiplication materials 8. The cover plate 3 has a certain absorption effect on neutrons. In addition to absorbing neutrons, the rear baffle 2 has a non-negligible effect on reflecting neutrons. Figure 1-3 shown.

[0027] Furthermore, the thickness of the tungsten armor is no more than 2 mm.

[0028] Furthermore, the breeder area 7 and the cooling baffle 9 are provided with cooling channels, and the rear baffle 2 and the cover plate 3 are provided with tritium extraction channels. The main effect of the cooling channel on the neutron experiment is that it reduces the average density of the structural components and reduces the loss term caused by the structural material absorbing neutrons.

[0029] Furthermore, the number of proliferation agent zones 7 is 5.

[0030] Furthermore, a multiplier container assembly is provided in the middle and upper part of the multiplier area 7, and a multiplier 10 is provided in the area of ​​the multiplier area 7 except for the multiplier container assembly. The multiplier 10 is lithium orthosilicate (Li4SiO4), and the lithium orthosilicate is a ball bed structure, and the diameter of the small ball is 0.8-1.2mm. The size and stacking method of the small balls in the ball bed affect the filling rate, the average density of the material, and further affect its neutron chemistry and tritium production performance.

[0031] Furthermore, the value-added agent container assembly includes a value-added agent container 71 and a plug 72. The value-added agent container 71 is provided with plugs 73 arranged in sequence along the axial direction, and the plugs 73 are provided with detection pieces 74. Figure 4 shown.

[0032] Furthermore, the neutron multiplying material 8 is beryllium, and the beryllium has a pebble bed structure, and the pebble bed diameter is 0.5-1.5 mm.

[0033] Furthermore, the cooling baffle 9 is made of low-activation steel CLF-1.

[0034] Furthermore, the first wall 1 , the rear baffle 2 , the cover plate 3 , the bottom plate 4 , the left side plate 5 and the right side plate 6 are made of low-activated steel CLF-1.

[0035] The helium-cooled fusion blanket experimental module will carry out high-precision evaluation and high-level experimental verification of the blanket tritium breeding ratio for the CFETR helium-cooled blanket, improve the technical level of fusion blanket neutronic verification, measurement technology and blanket tritium breeding performance evaluation in my country, accumulate independent tritium-producing blanket performance data, meet the urgent needs of ITER-TBM project development, and lay the foundation for the design of CFETR helium-cooled blanket engineering. It has important strategic significance for the sustainable development of my country's economy and society.

[0036] Tritium "self-sustainability" is a key link in the future commercial application of fusion reactors, and the breeder blanket is the basis for achieving tritium "self-sustainability". Achieving tritium "self-sustainability" through the research of helium-cooled fusion blanket experimental modules and related technologies and promoting the development of fusion energy technology is one of the fundamental ways to completely solve the energy problem, so it has broad application prospects.

[0037] The present invention is described in detail above in combination with specific implementation methods and exemplary examples. The above description is exemplary, not exhaustive, and is not limited to the disclosed embodiments; the above description cannot be understood as limiting the present invention. Those skilled in the art understand that, without departing from the spirit and scope of the present invention, the technical solution of the present invention and its implementation methods may be subjected to a variety of equivalent substitutions, modifications or improvements, all of which fall within the scope of the present invention; the protection scope of the present invention shall be subject to the attached claims.

Claims

1. A helium-cold fusion blanket experimental module device, characterized in that: The module device is provided with a first wall (1) containing tungsten armor, a proliferation agent area and a rear baffle (2) in sequence along the radial direction, and a cover plate (3), a bottom plate (4), a left side plate (5) and a right side plate (6) along the circumferential direction. The proliferation agent area includes a cavity formed by the first wall (1), the rear baffle (2), the cover plate (3), the bottom plate (4), the left side plate (5) and the right side plate (6); The multiplier zone is radially arranged in sequence from small to large with a plurality of multiplier zones (7) of different sizes, from the first wall (1) to the rear baffle (2); neutron multiplication materials (8) are arranged between the multiplier zones (7); and a cooling baffle (9) is arranged between the multiplier zones (7) and the neutron multiplication materials (8).

2. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: The thickness of the tungsten armor is no more than 2 mm.

3. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: The breeder area (7) and the cooling baffle (9) are provided with cooling channels, and the rear baffle (2) and the cover plate (3) are provided with tritium extraction channels.

4. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: The number of the proliferation agent zones (7) is 5.

5. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: A value-added agent container assembly is arranged in the middle and upper part of the proliferation agent zone (7), and a proliferation agent (10) is arranged in the proliferation agent zone (7) except for the region of the value-added agent container assembly. The proliferation agent (10) is lithium orthosilicate, and the lithium orthosilicate is a ball bed structure, and the diameter of the small balls is 0.8-1.2 mm.

6. The helium-cooled fusion blanket experimental module device according to claim 5, characterized in that: The multiplier container assembly comprises a multiplier container (71) and a plug (72), wherein plugs (73) arranged in sequence along the axial direction are arranged inside the multiplier container (71), and a detection piece (74) is arranged inside the plug (73).

7. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: The neutron multiplying material (8) is beryllium, and the beryllium is in a pebble bed structure, and the pebble bed diameter is 0.5-1.5 mm.

8. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: The material of the cooling baffle (9) is low-activation steel CLF-1.

9. The helium-cooled fusion blanket experimental module device according to claim 1, characterized in that: The first wall (1), the rear baffle (2), the cover plate (3), the bottom plate (4), the left side plate (5) and the right side plate (6) are made of low-activated steel CLF-1.

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