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CN-121983354-A - Tritium extraction device and method for multi-stage bubble tower type gas-liquid contactor

CN121983354ACN 121983354 ACN121983354 ACN 121983354ACN-121983354-A

Abstract

The invention provides a tritium extracting device and method of a multistage bubble tower type gas-liquid contactor, which are used for extracting tritium from helium-cooled lithium-lead proliferation cladding of a superconducting magnetic confinement fusion reactor, and comprise the following steps: the multistage series mechanism is arranged at the outlet of the helium-cooled lithium lead proliferation cladding and is used for extracting tritium dissolved in the eutectic lithium lead alloy through carrier band gas, and is formed by sequentially connecting the multistage GLC units in series, wherein the heights of the GLC units at each stage are gradually reduced, and the number of stages of the multistage series mechanism is more than or equal to ten. All levels of GLC units are communicated through connecting pipes arranged at different heights, and all levels of GLC units are arranged along the direction vertical to the horizontal plane, so that the problem of uneven liquid level of each GLC unit in the operation process is solved, and the overall operation stability and safety of the device are improved. Proved by verification, the extraction efficiency of the thirteen-stage serial multistage serial mechanism to tritium can reach more than 90%, and the efficiency requirement of the magnetic confinement fusion reactor on the self-sustaining operation of tritium can be met.

Inventors

  • HUANG KAI
  • ZHANG BIN
  • LV YONGPENG
  • Huang Zhaoding
  • RUAN SHIXIN
  • RAN PENG

Assignees

  • 上海电力大学

Dates

Publication Date
20260505
Application Date
20251226

Claims (7)

  1. 1. A multi-stage bubble-column gas-liquid contactor tritium extraction device for extracting tritium from helium-cooled lithium-lead proliferation cladding of a superconducting magnetic confinement fusion reactor, comprising: The multistage serial mechanism is arranged at the outlet of the helium-cooled lithium-lead proliferation cladding and is used for extracting the tritium dissolved in the eutectic lithium-lead alloy through carrier band gas, the multistage serial mechanism is formed by sequentially connecting a plurality of GLC units in series, The height of each stage of the GLC unit is gradually reduced, and the number of stages of the multistage serial mechanism is more than or equal to ten.
  2. 2. The multi-stage bubble column gas-liquid contactor tritium extraction device of claim 1, wherein: The GLC units of each stage are communicated through connecting pipes arranged at different heights, and the GLC units of each stage are arranged along the direction vertical to the horizontal plane.
  3. 3. The multi-stage bubble column gas-liquid contactor tritium extraction device of claim 1, wherein: Wherein, the structural material of the GLC unit is low-activation ferrite/martensite steel.
  4. 4. The multi-stage bubble column gas-liquid contactor tritium extraction device of claim 2, wherein: wherein the GLC unit comprises: A collection tube for contacting the eutectic lithium lead alloy with the carrier gas and extracting the tritium into the carrier gas; The lithium lead inlet is arranged at one end of the collecting pipe; the lithium lead outlet is arranged at one end of the collecting pipe, which is far away from the lithium lead inlet; the carrier gas inlet is arranged at one end of the collecting pipe, which is close to the lithium lead outlet; the carrier gas outlet is arranged at one end of the collecting pipe close to the lithium lead inlet, And the lithium lead outlet and the lithium lead inlet of the adjacent GLC unit are communicated through the connecting pipe.
  5. 5. The multi-stage bubble column gas-liquid contactor tritium extraction device of claim 1, wherein: wherein the carrier gas is helium.
  6. 6. The multi-stage bubble column gas-liquid contactor tritium extraction device of claim 4, wherein: Wherein the flow of the carrier gas is matched with the flow of the eutectic lithium lead alloy.
  7. 7. A method for extracting tritium by using the multi-stage bubble-column type gas-liquid contactor according to any one of claims 1 to 6, which is characterized by comprising the following steps: s1, introducing the eutectic lithium lead alloy into the GLC unit of the first stage from an outlet of the helium cooling lithium lead proliferation cladding; s2, introducing carrier gas into each stage of GLC unit, enabling the tritium dissolved in the eutectic lithium-lead alloy to be in contact with the carrier gas and transferring the tritium into the carrier gas; S3, sequentially flowing the eutectic lithium lead alloy through the GLC units until multi-stage extraction is completed; S4, collecting carrier gas and separating and recovering tritium.

Description

Tritium extraction device and method for multi-stage bubble tower type gas-liquid contactor Technical Field The invention relates to the technical field of nuclear fusion engineering, in particular to a tritium extraction device and method for a multi-stage bubble-column gas-liquid contactor. Background With the progressive exhaustion of fossil energy, research and design of commercial fusion reactors has become an important approach to solve the problem of future energy. Controllable nuclear fusion research starts in the 30 s of the 20 th century, and two major directions of Inertial Confinement Fusion (ICF) and Magnetic Confinement Fusion (MCF) are formed at present. Among them, the magnetically constrained tokamak (Tokamak) device is considered as the most promising solution for applications due to its relatively mature physical basis and engineering experience. The international thermonuclear fusion experimental reactor (ITER), european Union dominant nuclear fusion demonstration reactor (EU-DEMO) and Chinese fusion engineering experimental reactor (CFETR) all adopt the route. The cladding serves as a core component of the fusion device and plays roles of tritium proliferation, energy conversion, radiation shielding and the like. To maintain continuous operation of the fusion reactor, tritium is extracted from the cladding by a Tritium Extraction System (TES), separated and purified, and then re-injected into the core, thereby realizing closed-loop circulation of fuel. The cladding is divided into a solid state type and a liquid state type according to the form of the proliferation agent, wherein the liquid lithium lead cladding has the advantages of good adaptability, high tritium proliferation rate, excellent thermophysical property and the like, and is applied to the schemes of ITER and DEMO. In helium-cooled lithium lead breeder cladding (HCLL-BB), liquid lithium lead alloy (Pb-15.7 Li) is used as neutron multiplier and tritium breeder simultaneously. Existing tritium extraction techniques include gas-liquid contact (GLC), vacuum Permeation (PAV) and vacuum sieve plate (VST). Among them, GLC was identified as a benchmark for tritium extraction in ITER fusion plants because of its technical maturity, ease of manufacture, and high reliability. However, the extraction efficiency of the existing single-tower GLC is only about 30%, and the liquid level in the tower is difficult to keep balanced in the operation process, so that the long-term stability and the safety are affected. Accordingly, there is a need for an improved multistage series structure to increase overall extraction efficiency and solve the level imbalance problem. Disclosure of Invention The invention aims to solve the problems and aims to provide a tritium extraction device and a tritium extraction method for a multi-stage bubble-column type gas-liquid contactor. The invention provides a tritium extracting device of a multistage bubble tower type gas-liquid contactor, which is used for extracting tritium from helium-cooled lithium-lead proliferation cladding of a superconducting magnetic confinement fusion reactor, and has the characteristics that: the multistage series mechanism is arranged at the outlet of the helium-cooled lithium lead proliferation cladding and is used for extracting tritium dissolved in the eutectic lithium lead alloy through carrier gas, and is formed by sequentially connecting the multistage GLC units in series, wherein the heights of the GLC units at each stage are gradually reduced, and the number of stages of the multistage series mechanism is more than or equal to ten. The tritium extraction device of the multi-stage bubble tower type gas-liquid contactor can be characterized in that all stages of GLC units are communicated through connecting pipes arranged at different heights, and all stages of GLC units are arranged along the direction vertical to the horizontal plane. The tritium extraction device of the multi-stage bubble-column gas-liquid contactor can be characterized in that the structural material of the GLC unit is low-activation ferrite/martensitic steel. The multi-stage bubble tower type gas-liquid contactor tritium extraction device is characterized in that the GLC unit comprises a collecting pipe, a lithium lead inlet, a lithium lead outlet, a carrier gas inlet and a carrier gas outlet, wherein the collecting pipe is used for enabling eutectic lithium lead alloy to be in contact with carrier gas and extracting tritium into the carrier gas, the lithium lead inlet is arranged at one end of the collecting pipe, the lithium lead outlet is arranged at one end of the collecting pipe, which is far away from the lithium lead inlet, the carrier gas inlet is arranged at one end of the collecting pipe, which is close to the lithium lead outlet, the carrier gas outlet is arranged at one end of the collecting pipe, which is close to the lithium lead inlet, and the lithium lead outlet and the lithium lead inl