Experimental system for testing performance of methyl iodide adsorption material

An experimental system and iodine adsorption technology, applied in the field of nuclear radiation protection, can solve the problems of human injury, difficulty in measurement, and low content of organic iodine, and achieve the effects of comprehensive functions, reduced experimental errors, and high measurement accuracy

Active Publication Date: 2021-09-17
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

The radioactive substances in the exhaust gas mainly exist in the form of aerosols (CsI, CsOH), gaseous elemental iodine and gaseous organic iodine. Considering that the content of organic iodine is small and difficult to measure in previous nuclear power projects, there is no requirement to filter organic iodine. However, after the Fukushima nuclear accident, it was found that the content of organic iodine in the released radioactive substances was relatively large, and organic iodine was easily absorbed by the thyroid gland of the human body and caused harm to the human body. Therefore, for the new The first-generation containment filtration and drainage system needs to improve its filtration efficiency for organic iodine
[0003] At present, there are few domestic studies on the performance of organic iodine adsorption materials. A tritium gas adsorption performance experimental device and method designed in patent 202010542892.3 is designed for the adsorption performance research of adsorbents under normal temperature and pressure conditions, but it is not applicable. under complex thermal conditions
[0004] The experimental research on the adsorption performance of methyl iodide abroad is relatively in-depth, and the literature "Silver-mordenite forradiologic gas capture from complex streams: Dual catalytic CH 3 In "I decomposition and I confinement", the experimental device is designed for the performance test of the adsorption material under the condition of multi-component gas. The multi-adsorption bed series design is used to conduct experimental research on the influence of complex gas components under severe accident conditions. The design uses an inductor Coupling plasma mass spectrometer and gas chromatography-flame ionization detector and other instruments for measurement, but does not consider the influence of thermal parameters, this device is not suitable for high temperature, high pressure and high steam ratio in terms of structure and measurement function
Literature "Effects of water vapor and temperature on the retention of radiotoxic CH 3 In "I by silver faujasite zeolites", the experimental device is designed for the performance test experiment of the adsorption material under different temperature and steam share conditions, which is used to study the influence of accident conditions on its performance. The activated carbon box is used to absorb the gas and measure the gas concentration based on the radioactive content of the gas. , this device is not suitable for high-pressure experimental environments, and the measurement method based on the radioactive content of the gas is relatively harsh

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  • Experimental system for testing performance of methyl iodide adsorption material
  • Experimental system for testing performance of methyl iodide adsorption material
  • Experimental system for testing performance of methyl iodide adsorption material

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Embodiment Construction

[0047] Specific embodiments of the present invention is described in further detail below in conjunction with the accompanying drawings and.

[0048] like figure 1 A method for methyl iodide adsorbent performance testing experimental system shown, can be applied to up to 200 ℃, 1MPa at the high temperatures and pressures, including 1, 2 compressor steam supply means, the supply means methyl iodide 3, steam-water separation apparatus 4, 5 experimental adsorption bed, the bed control 6, a condenser A7, cooling water tank 8, a pump 9, BlO condenser, steam separator A11, steam separator B12, GC 13, a data acquisition system 14 the temperature control system 15.

[0049] Means methyl iodide, and 2 are connected to a steam supply device 3 is supplied through the two branch pipes at the rear of the compressor 1.

[0050] Behind the steam supply means 2 and methyl iodide supply device 3 is connected to the separation means 4 soda. Two manifolds provided at the rear end of the steam-water ...

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Abstract

The invention relates to the technical field of nuclear radiation protection, and particularly discloses an experimental system for testing the performance of a methyl iodide adsorption material. S double-bed body structure with an experimental adsorption bed and a control bed symmetrically arranged is adopted and can be used for comparison verification of adsorption efficiency data to remove the influence of the adsorption performance of a substrate material. Meanwhile, the control bed can be used for working condition adjustment at the initial stage of the experiment, and influences of initial working condition adjustment and gas flow at the preheating stage of the experiment adsorption bed and the control bed on the performance of the adsorption material are reduced. According to the invention, performance testing can be carried out on different methyl iodide adsorption materials under thermal conditions of large-range temperature, pressure and the like, the functions are comprehensive, other matching devices are not needed, and the measurement precision is high.

Description

Technical field [0001] The present invention belongs to the technical field of nuclear radiation protection, particularly relates to a system for the experimental methyl iodide adsorbent performance testing. Background technique [0002] After a serious nuclear power plant accident containment pressure will be gradually increased, in the case of containment cooling system failure may be due to overpressure and damage the integrity of the containment, resulting in leakage of radioactive material. Containment system using active filter drain reduce containment pressure relief mode, so that the pressure does not exceed the containment vessel carrying limits, to ensure the integrity of the containment; while exhaust gas in order to prevent harm to the environment caused by radiation, the containment filter means disposed on the filter of the exhaust system the exhaust gas pressure relief line of radioactive material was filtered. Radioactive substances in the exhaust gas mainly in th...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01N23/06G01N30/02
CPCG01N23/06G01N30/02
Inventor 邢继刘长亮孙中宁朱京梅谷海峰王晓江周艳民荆春宁孙超杰杨理烽张志明刘嘉维张卫李栋梁丁亮赵斌王佳卓李亚飞
Owner CHINA NUCLEAR POWER ENG CO LTD
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