[en] A radioactive liquid waste evaporation processing system of xx project was debugged. During the commissioning, it was aimed to obtain purification factor by adjusting the quantity, liquid level of evaporator, fresh steam flow and other system parameters to change the system operating conditions, and analysis system purification factor. Debugging results show that for the system, purifying coefficient was the highest when the evaporator liquid level at 500 mm. The highest purification factor for evaporation capacity 1 m³/h. System fluctuate when running in variable conditions, and purification coefficient decrease. Analysis of the relationship between the parameters of system operation, from the prospective of stability and purifying effect, a reasonable improvement of the original control system was raised. (authors)

[en] At present, there is no instrument for waste resin or water interface measurement at home and abroad. Based on the magnetostrictive principle, a measurement method of waste resin/water interface using driving device as auxiliary means is proposed. On this basis, the overall design of the measurement system is carried out, and the corresponding measurement system is designed. The designed system is verified by experiments. The test results show that the measurement system realizes the measurement of waste resin or water interface, and is with the characteristics of high measurement accuracy, miniaturization, modularization, adjustable lifting speed, and easy installation and maintenance. The successful development of the system solves the problem of waste resin or water interface measurement, and it is worthy of promotion and further engineering application in the process of radioactive waste liquid treatment. (authors)

[en] In order to eliminate the leakage of residual waste liquid into the environment after the damage of large-scale underground medium and low level radioactive liquid waste storage tank. In this paper, a low cost and feasible principle scheme of residual liquid retrieval at the bottom of the tank based on the intelligent remote control vehicle + micro self-priming pump is proposed. In the scheme, the intelligent remote control vehicle is used as the residual liquid approaching device to pull waste liquid pipe of micro self-priming pump to the lowest point of the tank. Micro self-priming pump as residual liquid transfer equipment to complete the residual suction work. The scheme has the Advantages of simple process equipment, low price, small amount of secondary waste, convenient operation and strong engineering feasibility. (authors)

[en] In this paper, the large-screen system in the pilot control room of the control center is utilized as an example to analyze the solution of the large-screen splicing system. Based on this analysis, the large-screen splicing system is explored and the diversification solution of the large-screen system in the construction of the new center is given. For the he typical large-screen splicing mainstream technologies: LCD splicing, small-pitch LED display and DLP splicing, the actual effects, the cost, the installation environment, the life, after-sales service are researched and analyzed. Finally, this paper constructs an evaluation system for the large-screen splicing system in the main control room of the center and shows a comprehensive solution including the selection, installation and maintenance. (authors)

[en] The effective disposal of radioactive waste liquid is the precondition for the rapid development of nuclear industry all over the world, and the current situation and development direction of its key technologies are the focus of attention of the nuclear industry in China. This paper introduces several traditional methods of radioactive waste liquid treatment and the emerging new technology options, summarizes the principles, advantages and disadvantages of various methods, and discusses the research direction and development trend of radioactive waste liquid treatment technology in the future. (authors)

[en] In order to retrieve the waste from a waste pit with small opening, the silica sands packaged in a canvas bag was used to shield the intermediate level waste (ILW). The shielding depth was calculated with QAD-CG, and the filling and retrieve of silica sands was well prepared and practiced. The dose rate at the opening was reduced from 4.28 Gy/h to 4.49 μGy/h. The waste retrieve work went on smoothly. The personnel collective dose to set and dismantle the silica sands shielding facility is 0.45 men · mSv in total. (authors)