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Novel test blanket testing device for tritium breeding and heat rejection

A technology of experimental cladding and testing equipment, applied in thermonuclear fusion reactors, nuclear reactors, nuclear power generation, etc.

Inactive Publication Date: 2016-07-13
SOUTHWESTERN INST OF PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0003] In the ITER device, the experimental cladding module will face the impact of high-energy, high-flux neutrons and high thermal loads. How to ensure that the experimental cladding module does not affect the safe operation of the ITER device and realize tritium multiplication under such extreme conditions and high-efficiency energy extraction are two major experimental goals, which are very challenging

Method used

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  • Novel test blanket testing device for tritium breeding and heat rejection
  • Novel test blanket testing device for tritium breeding and heat rejection
  • Novel test blanket testing device for tritium breeding and heat rejection

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Embodiment Construction

[0013] The present invention is described in detail below in conjunction with accompanying drawing and embodiment:

[0014] like figure 1 , 2 As shown, a new experimental cladding test device for tritium breeding and heat removal includes submodules 2, and each submodule 2 includes a U-shaped first wall 1, two upper and lower cover plates 8 and a submodule rear plate system 9 As the outer boundary, there is a middle plate 10 inside, and two sets of double-layer U-shaped helium cooling plates 13 are installed on both sides of the middle plate 10. The double-layer U-shaped helium cooling plates 13 and the middle plate 10 divide the interior of the submodule into favorable Breeding neutron multiplication area 12 and tritium breeding area 11, installed on the sub-module rear plate system 9 with the double-layer U-shaped helium cooling plate 13, the helium cooling pipe 4 communicated with the cover plate 8 and the middle plate 10 and the helium cooling pipeline 4 connected with th...

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Abstract

The invention relates to a novel test blanket testing device for tritium breeding and heat rejection. The novel test blanket testing device comprises sub-modules; each sub-module comprises a first U-shaped wall, an upper cover plate, a lower cover plate and a sub-module backboard system so as to act as an outer boundary; a middle plate is arranged in each sub-module; two sides of the middle plate are provided with two groups of double-layer U-shaped helium cooling plates; the internal part of the sub-module is divided into neutron multiplication regions and tritium breeding regions by the double-layer U-shaped helium cooling plates and the middle plate; and the sub-module backboard system is provided with a helium cooling pipeline communicated with the double-layer U-shaped helium cooling plates, the cover plates and the middle plate and a tritium extraction pipeline communicated with the tritium breeding regions and the neutron multiplication regions. According to the novel test blanket testing device, a modularized structure is adopted; the double-layer U-shaped cooling plates are adopted in the sub-modules, and structural arrangement, which is conducive to tritium breeding, of the neutron multiplication regions and the tritium breeding regions, is formed; and a bypass is adopted, and therefore, control on the flow rate of a cooling agent can be benefitted, and realization of tritium breeding and efficient energy extraction under the premise of stable and safe operation of an ITER test window can be ensured.

Description

technical field [0001] The invention belongs to a fusion energy cladding testing device, in particular to a novel experimental cladding testing device for tritium multiplication and heat removal. Background technique [0002] In the field of controlled thermonuclear fusion research, tritium breeding and high-efficiency energy extraction technology are the key technologies to realize magnetic confinement thermonuclear fusion reaction power generation. The experimental cladding module will be used as an important component to perform functional tests of tritium breeding and energy extraction on the International Thermonuclear Experimental Reactor (ITER). The ITER device has very strict requirements for the experimental cladding module. In order to realize the above two key technologies of nuclear fusion reactions, a new type of modular design is proposed. The sub-module directly faces the plasma, and the functional materials are composed of two double-layer U-shaped plates. T...

Claims

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Application Information

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IPC IPC(8): G21B1/11G21B1/00
CPCY02E30/10
Inventor 胡刚冯开明赵周王琦杰曹启祥张国书陈颜静向兵张龙赵奉超白孟
Owner SOUTHWESTERN INST OF PHYSICS
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