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Tritium breeding blanket system based on lithium deuteroxide heavy water solution

A technology for lithium deuterium oxide and tritium multiplication, applied in nuclear reactors, nuclear power generation, climate sustainability, etc., to achieve the effects of easy online refueling, easy processing, and improved safety

Inactive Publication Date: 2014-01-08
罗天勇 +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0008] The purpose of the present invention is to provide a new fusion reactor cladding tritium multiplication solution, to solve the deuterium-tritium fusion technology research device after the International Thermonuclear Experimental Reactor (ITER), fusion engineering technology experimental reactor and fusion demonstration reactor. Sustainability problem

Method used

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  • Tritium breeding blanket system based on lithium deuteroxide heavy water solution
  • Tritium breeding blanket system based on lithium deuteroxide heavy water solution

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Embodiment 1

[0024] The tritium breeding cladding system for the fusion reactor engineering technology experiment platform based on the heavy aqueous solution of lithium deuterium oxide is as follows: figure 1 As shown, the system consists of three parts: the tritium breeding cladding body, the primary circuit system, and the tritium enrichment system. The tritium breeding cladding body and the primary circuit system are connected through the fluid inlet and the fluid outlet. The vapor outlet of the vacuum vapor-liquid separation device is connected to the tritium enrichment system.

[0025] The system uses heavy water saturated solution of lithium deuterium oxide as the tritium breeding agent and coolant, wherein the molar concentration of lithium deuterium oxide is between 5mol / l, the inlet temperature of the tritium breeding cladding body is 120°C, the outlet temperature is 150°C and the working pressure is 1MPa . This parameter is based on the consideration that the fusion reactor eng...

Embodiment 2

[0030] Tritium breeding cladding system for fusion demonstration reactor based on heavy deuterium oxide lithium solution. The system consists of three parts: tritium breeding cladding body, primary loop system and tritium enrichment system. Tritium breeding cladding body and primary loop system pass through The fluid inlet and the fluid outlet are connected with two nozzles, and the primary loop system is connected with the tritium enrichment system through the steam outlet of its decompression gas-liquid separation device.

[0031] The system uses a heavy water saturated solution of lithium deuterium oxide as a tritium breeding agent and coolant, wherein the molar concentration of lithium deuterium oxide is between 5.5mol / l, the inlet temperature of the tritium breeding cladding body is 260°C, and the outlet temperature is 280°C. The working pressure is at 8MPa.

[0032] The primary circuit system consists of a voltage stabilizer, a heat exchanger, a pump, a decompression vap...

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Abstract

The invention relates to a tritium breeding blanket system based on lithium deuteroxide heavy water solution, which consists of a tritium breeding blanket body, a primary loop system and a tritium enrichment system. Heavy water saturated solution of lithium deuteroxide is used as tritium breeder and coolant. Since the system unifies the tritium breeder and the coolant, a blanket structure is simplified and the manufacturing of the blanket body is facilitated; since the tritium breeder has flowability, online refueling is easy to realize. Compared with a traditional liquid blanket system, the system avoids the problems of magnetic flow caused by liquid metal flowing and the corrosion caused by liquid metal to structural materials and improves the safety of the blanket system. A primary loop and heavy water tritium extraction technology related to the system has already been applied on a large scale in heavy water reactors. Compared with the existing solid and liquid tritium breeding blanket scheme, the technology is mature and reliable.

Description

technical field [0001] The invention belongs to the technical field of fusion tritium breeding cladding, and in particular relates to a new fusion tritium breeding cladding system scheme, which is used to solve deuterium-tritium fusion technology research devices and fusion engineering technology experiments after the International Thermonuclear Experimental Reactor (ITER) The problem of tritium self-sustainability of fusion reactor and fusion demonstration reactor. Background technique [0002] According to the current development trend of magnetic confinement plasma fusion control technology, the magnetic confinement fusion demonstration reactor after the International Thermonuclear Experimental Reactor (ITER) will mainly use deuterium-tritium as the basic fuel. Deuterium is relatively abundant in nature, but tritium is extremely rare in nature (the total amount in the atmosphere is less than 1 kg), and tritium self-sustainment must be achieved through the tritium breeding...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21B1/11G21B1/13
CPCY02E30/128Y02E30/10
Inventor 罗天勇张建利
Owner 罗天勇
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