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Beryllium-based liquid cladding layer based on silicon carbide tube

A technology of silicon carbide tube and cladding, applied in the field of fusion reactor engineering, which can solve the problems of easy corrosion of steel lithium-lead flow channel, insufficient tritium multiplication capacity, immature MHD effect mitigation measures, etc., to avoid material corrosion problems, weaken MHD effect, effect of improving thermoelectric conversion efficiency

Active Publication Date: 2020-10-30
HEFEI INSTITUTES OF PHYSICAL SCIENCE - CHINESE ACAD OF SCI +1
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Problems solved by technology

[0006] In order to overcome the shortcomings of insufficient tritium multiplication capacity in the rear area of ​​the liquid cladding, easy corrosion of the steel lithium-lead flow channel, and immature mitigation measures for the MHD effect, in view of the fact that the fission reactor silicon carbide fuel cladding tube technology has become increasingly mature, the present invention designs a A fusion reactor liquid cladding based on silicon carbide tubes and solid beryllium-titanium alloy body to increase the outlet temperature of TBR and liquid lithium-lead to meet the requirements of China Fusion Engineering Test Reactor (CFETR) to demonstrate tritium self-sustainability and high-efficiency fusion power generation

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Embodiment Construction

[0021] The technical solutions in the embodiments of the present invention are clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Apparently, the described embodiments are only some of the embodiments of the present invention, but not all of them. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without making creative efforts belong to the protection scope of the present invention.

[0022] According to an embodiment of the present invention, such as figure 1 As shown, a beryllium-based liquid cladding based on silicon carbide tubes mainly includes a U-shaped first wall (1), upper / lower cover plates (2-1 / 2-2), reinforcement plates (3), neutron Multiplier (4), cooling water inlet / outlet header (5-1 / 5-2), lithium lead runner (6) and back plate (7). Among them, the U-shaped first wall (1) is welded with the upper / lower cover plate (2-1 / 2-2)...

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Abstract

The invention discloses a beryllium-based liquid cladding layer based on a silicon carbide tube; a U-shaped first wall processed by low-activation steel is welded with an upper / lower cover plate, a reinforcing plate and a cooling water inlet header to form a plurality of cavities, and the cavities are supported by a back plate. A high-temperature and high-pressure water cooling agent is introducedinto a parallel first wall cooling water flow channel in the U-shaped first wall, so that the first wall of the cladding layer is cooled. A neutron multiplying agent for beryllium titanium alloy processing is arranged in the cavities, the silicon carbide lithium lead flow channel penetrates through a reinforcing plate and the neutron multiplying agent, lithium lead rapidly flows in the silicon carbide flow channel, and cladding layer tritium production and multiplication area heat removal are achieved. The cladding layer tritium propagation rate can be greater than 1.2 through reasonable proportioning of the liquid lithium lead and the beryllium titanium neutron multiplying agent; a silicon carbide tube which is resistant to high temperature and corrosion and good in electrical insulationis adopted as the lithium lead flow channel, the problems of the MHD effect and corrosion in the cladding layer can be effectively avoided, and the cladding layer outlet temperature and the fusion reactor thermoelectric conversion efficiency are improved.

Description

technical field [0001] The invention belongs to the technical field of fusion reactor engineering, and mainly relates to a beryllium-based liquid cladding based on a silicon carbide tube. Background technique [0002] The development of safe and efficient fusion energy has been included in the medium and long-term development plan of my country's nuclear energy field. At present, my country is conducting the design and research of the China Fusion Engineering Test Reactor (CFETR). Demonstrating fusion energy power generation and tritium self-sustainability, and achieving cladding tritium breeding rate TBR ≥ 1.1 are the main design goals proposed by CFETR. [0003] The tritium breeding envelope is the core component of the fusion reactor, and its main function is to achieve tritium self-sustainability, discharge nuclear heat and plasma heat flow, and provide radiation shielding. In response to these functional requirements, scholars at home and abroad have proposed a variet...

Claims

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Application Information

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IPC IPC(8): G21B1/11G21B1/13
CPCG21B1/11G21B1/13Y02E30/10
Inventor 陈磊刘松林李敏祝庆军卢棚蒋科成赵雪丽马学斌倪明玖陈龙
Owner HEFEI INSTITUTES OF PHYSICAL SCIENCE - CHINESE ACAD OF SCI
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