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Device for desorbing various nuclides in graphite

A graphite and desorption technology, applied in measuring devices, nuclear engineering, instruments, etc., can solve the problems of easy leakage, difficult collection and measurement, etc., and achieve the effect of easy collection and measurement

Active Publication Date: 2021-06-22
SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Heat treatment requires graphite to be heated to a high temperature, and in a high temperature environment, the gaseous tritium, carbon-14, chlorine-36 and its isotopes desorbed from graphite are easy to leak in conventionally designed reactors, and it is not easy to completely collect and measure them

Method used

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  • Device for desorbing various nuclides in graphite

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Embodiment Construction

[0021] In order to make the object, technical solution and advantages of the present invention clearer, the present invention will be described in further detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described here are only used to explain the present invention, not to limit the present invention.

[0022] It should be noted that when an element is referred to as being "mounted on", "fixed on" or "disposed on" another element, it can be directly on the other element or there may be intervening elements at the same time. When an element is referred to as being "connected to" another element, it can be directly connected to the other element or intervening elements may also be present.

[0023] It should also be noted that the orientation terms such as left, right, up, and down in the embodiments of the present invention are only relative concepts or refer to the normal use state of the product,...

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Abstract

The present invention discloses a device for desorbing various nuclides in graphite. The device comprises a furnace body, a sample cup is arranged in the furnace body, an induction heating coil and a controller are arranged outside the furnace body, the induction heating coil is located at the sample cup, the induction heating coil is electrically connected with the controller, an air inlet and an air outlet are formed in the furnace body, the air outlet is connected with a vacuum device, and the vacuum device is electrically connected with the controller. The gas inlet is connected with an inert gas supply device. The graphite sample can be directly heated through the induction heating coil on the premise that the whole furnace body is not heated, so that radionuclides or isotopes in the graphite sample can be desorbed under the high-temperature condition, and the phenomenon that desorbed gaseous nuclides leak due to the fact that the temperature of the furnace body is too high is avoided. Before heating, the furnace body is in a vacuum state through the vacuum device, so that the furnace body is prevented from being influenced by impurity gas in air in the experiment process, and after desorption is completed, inert gas is guided into the furnace body through the inert gas supply device, so that the inert gas carries out desorbed radionuclides or isotopes, and the radionuclides or isotopes are easy to collect.

Description

technical field [0001] The invention relates to the technical field of graphite desorption devices, in particular to a device for desorbing various nuclides in graphite. Background technique [0002] Graphite has always been an important material in a large number of reactors. All reactors that use graphite in the reactor are collectively called graphite reactors. Early graphite reactors appeared during World War II, so many graphite reactors were mainly built for plutonium production at that time. Subsequently, the graphite stack has also been greatly developed as a stack type for power generation. According to the different coolants used, subsequent graphite stacks are further divided into graphite gas-cooled stacks and graphite water-cooled stacks. A large amount of nuclear graphite is used in graphite piles of various nuclear power plants. In addition, there are a large number of graphite piles for research worldwide. According to IAEA statistics, there are more than ...

Claims

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Application Information

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IPC IPC(8): G21F9/00G01J5/00
CPCG21F9/007G01J5/00
Inventor 刘卫邓珂张铭军钱楠张钦曾友石
Owner SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI