Test blanket module for international thermonuclear experimental reactor with low toroidal field waviness

An experimental cladding module and thermonuclear fusion technology, applied in the field of experimental cladding modules of the International Thermonuclear Experimental Reactor, can solve problems such as the difficulty of connecting different materials

Inactive Publication Date: 2013-07-03
SOUTHWESTERN INST OF PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Therefore, it can be considered to replace the ferromagnetic RAFM with non-ferromagnetic 316LN on the rear plate, but the problem of the connection between 316LN and RAFM has been difficult to solve in the technical solution of replacing ferromagnetic RAFM with non-ferromagnetic 316LN

Method used

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  • Test blanket module for international thermonuclear experimental reactor with low toroidal field waviness

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Embodiment 1

[0026] The present invention is a method for reducing the content of ferromagnetic structural material CLF-1 in CN HCCB TBM, the purpose of which is to reduce the ferromagnetism of CN HCCB TBM on the basis of meeting the functional requirements of CN HCCB TBM and without greatly changing the overall design of existing CN HCCB TBM The use of substances, thereby reducing the toroidal magnetic field ripple of the ITER magnetic confinement device caused by the CNHCCB TBM.

[0027] Specific technical solutions include:

[0028] 1. The rear plate of CN HCCB TBM adopts non-ferromagnetic material SS 316LN-IG instead of CLF-1 as the structural material;

[0029] 2. The first wall 1 of CN HCCB TBM, the tritium breeding area 2, the upper and lower cover plates 4, and the shelf 5 still use CLF-1 as the structural material;

[0030] 3. Introduce an intermediate transition layer structure at the pipeline interface 6 between the first wall 1 of the CN HCCB TBM, the tritium breeding area 2, ...

Embodiment 2

[0034] A method of reducing the content of ferromagnetic structure material CLF-1 in CN HCCB TBM of the present invention aims at reducing the ferromagnetism of CN HCCB TBM on the basis of meeting the functional requirements of CN HCCB TBM and without substantially changing the overall design of existing CN HCCB TBM The use of materials, thereby reducing the tokamak device ring magnetic field ripple caused by the CNHCCB TBM.

[0035] Specific measures include:

[0036] 1. Prepare Inconel718 and SS 316LN-IG uniformly mixed composite material with a molar ratio of 1:1 by powder metallurgy method, and roll it into a 1-3mm plate;

[0037] 2. Using the vacuum thermal diffusion process to roll a multi-layer composite board consisting of four layers of CLF-1 layer, Inconel718 layer, Inconel718 and SS 316LN-IG composite layer, and SS 316LN-IG layer; the CLF-1 layer is 1mm thick, Inconel718 layer 2mm thick, Inconel718 and SS 316LN-IG composite layer 2mm thick, SS 316LN-IG layer 1mm th...

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Abstract

The invention belongs to the technical field of test blanket modules (TBMs), and particularly relates to a test blanket module for an international thermonuclear experimental reactor (ITER) with low toroidal field waviness, which can reduce the toroidal magnetic field waviness caused by a ferromagnetic material in the test blanket module. A front end structure of the test blanket module comprises a first wall, a tritium breeding region, an upper and lower cover plate and a separation rack that adopt RAFM (Reduced Activation Ferritic / Martensitic) steel as a structural material; a rear plate of the test blanket module adopts a non-ferromagnetic material 316LN as a major structural material; interfaces of the front end structure and the rear plate are connected by a middle transition layer structure; and the middle transition layer is a nickel alloy at the working condition temperature of 300-400 DEG C, and is a composite layer of the nickel alloy and the 316LN material at the working condition temperature of 400-500 DEG C. The influence of the TBM on the toroidal field waviness of the ITER is reduced greatly, the nickel alloy is adopted as the middle transition layer in a member design, so that the anisotropic material connection between the RAFM steel and the 316LN steel is realized, and the effect is obvious.

Description

technical field [0001] The invention belongs to the technical field of the experimental cladding module (TBM) of the International Thermonuclear Experimental Reactor (ITER), and in particular relates to a low ring field ripple that can reduce the circular magnetic field ripple degree caused by the ferromagnetic material in the experimental cladding module degree of the ITER experimental cladding module. Background technique [0002] The International Thermonuclear Experimental Reactor (ITER) project is an international magnetic confinement tokamak experimental device designed to verify the feasibility of full-scale controllable nuclear fusion technology under planning and construction. The Experimental Blanket Module (TBM) is a component developed by the member countries of the ITER International Cooperation Organization to carry out physical and engineering experiments on ITER, and is used to simulate and test technologies related to the cladding of future fusion reactors. ...

Claims

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Application Information

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IPC IPC(8): G21B1/11G21B1/13
CPCY02E30/10
Inventor 罗天勇钟原
Owner SOUTHWESTERN INST OF PHYSICS
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