Device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases

A recovery device and fusion reactor technology, applied in the field of fusion reactors, can solve problems such as the adverse effects on the service life of Pd alloy membrane separators and system stability, the processing speed of CAPER process and insufficient tritium retention in the system, and the reduction of impurity gas content, etc. To avoid adverse effects, reduce tritium retention, and reduce the amount of impurity gas

Inactive Publication Date: 2016-09-07
INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF
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Problems solved by technology

However, in this process, the unit for recovering combined deuterium and tritium (ie catalytic reaction-membrane separation unit and catalytic exchange membrane reaction unit) takes a long time and costs a lot
At the same time, in recent years, designers of fusion reactors have improved the materials facing the plasma, and the selected materials do not contain carbon elements, which greatly reduces the content of impur

Method used

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  • Device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases

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Effect test

Embodiment 1

[0048] The composition and content of the ash gas are as follows: Q 2 99.10%, He 0.50%, Q 2 O 0.10%, CQ 4 0.08%, CO 0.06%, CO 2 0.03%, N 2 0.10%, O 2 0.03%.

[0049] In this example, since the impurity gas content is very low (less than 1.0%), it has little effect on the performance of the Pd alloy film, and the front and rear stages of the cryopump desorb simultaneously to obtain gas , directly into the Pd alloy membrane separation unit, the permeate gas of the Pd alloy membrane separation unit is high-purity (>99.999%) Q 2 (denoted as gas ),gas The contents of protium, deuterium and tritium (volume percentage) are 2.0%, 48.7% and 49.3% respectively, which directly enter the tritium storage system. The tail gas separated by the Pd alloy membrane separation unit (denoted as tail gas ) contains a small amount of Q 2 and He, Q 2 O, CQ 4 , CO, CO 2 , N 2 , O 2 and other impurity gases are stored in the buffer device (in this embodiment, the buffer device ad...

Embodiment 2

[0052] In the present embodiment, the component and content of ash exhaust gas are as follows: Q 2 94.10%, He 2.80%, Q 2 O 0.80%, CQ 4 0.65%, CO 0.35%, CO 2 0.28%, N 2 0.90%, O 2 0.12%.

[0053] In this example, due to the relatively high content of impurity gases, the front and rear stages of the cryopump were desorbed separately, and the low-temperature molecular sieve column in the front stage was desorbed at room temperature to obtain tail gas , the subsequent helium-refrigerated cryopump desorbs the gas at 77K . gas The main component is Q 2 and He, exhaust Contains a small amount of Q 2 and He, Q 2 O, CQ 4 , CO, CO 2 , N 2 , O 2 and other impurity gases. gas Enter the Pd alloy membrane separation unit to get the gas and exhaust ,gas The contents of protium, deuterium and tritium are 11.0%, 44.2% and 44.8% respectively. due to gas The content of protium in the medium is relatively high, and it enters the filling of Al 2 o 3 +1%SiO2 2...

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Abstract

The invention provides a device and method for quickly recovering deuterium and tritium in fusion reactor discharged ash gases. The device is divided into a main path and a branch path according to effects and necessities of various units in treatment processes. The main path only comprises a cryogenic pump and a Pd alloy film separating unit, and 96% or more deuterium and tritium fuels in the discharged ash gases can be recovered by virtue of the two units. The method for quickly recovering deuterium and tritium in the fusion reactor discharged ash gases is short in treatment time, and better meets requirements for quick recovery of the deuterium and tritium fuels; and meanwhile, the recovery process is simplified, which is conducive to reduction of the retention volume of tritium in a system, thereby avoiding impurity gases from causing adverse effects on a Pd alloy film separator. Moreover, a small amount of deuterium and tritium not recovered by the main path are recovered by the branch path, thereby ensuring relatively high recovery efficiency. The device and method for quickly recovering deuterium and tritium in the fusion reactor discharged ash gases have the advantages of short treatment cycle, simple process, high recovery rate, good system stability, long service life and the like, and can meet design requirements of existing fusion reactors.

Description

technical field [0001] The invention belongs to the field of fusion reactors, and in particular relates to a fast recovery device and method for deuterium and tritium in fusion reactor ash exhaust gas. Background technique [0002] With the shortage of fossil fuels and the increasing seriousness of environmental pollution, fusion energy has gradually attracted people's attention. In the development of fusion energy, the deuterium-tritium fuel cycle is an engineering technical problem that must be solved, and it is also the basis for realizing commercial applications. Since the reaction rate of deuterium-tritium in the fusion process is very low, a large amount of unreacted deuterium-tritium exists in the plasma exhaust gas. From the perspective of safety, environmental protection and economy, the exhaust gas must be treated, and the deuterium-tritium fuel in it must be treated. to recycle. [0003] The deuterium-tritium fuel recovery in the exhaust gas is mainly completed ...

Claims

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Application Information

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IPC IPC(8): C01B4/00
CPCC01B4/00
Inventor 熊亮萍王和义龚宇岳磊侯京伟陈晓军刘云怒夏修龙肖成建张勤英
Owner INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF
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