AbstractAbstract
[en] Progress report on nuclear science and technology in China (Vol.5) includes 10 books totally. This is the tenth one. It includes two parts. The first part, Nuclear Measurement and Analysis sub-volume includes 8 articles communicated on the 2017 Academic Annual Meeting of China Nuclear Society, Weihai, 16-18 Oct 2017
Primary Subject
Source
Apr 2018; 51 p; China Atomic Energy Press; Beijing (China); 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; ISBN 978-7-5022-8776-4;
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Book
Literature Type
Conference; Progress Report
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Li Ziqiang; Liu Malin; Liu Xiaoxue; Zhang Kaihong; Zhao Hongsheng
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
AbstractAbstract
[en] In the process of HTR operation, fuel elements are inevitably worn because of friction and collision. Therefore, the study of friction and wear behavior of spherical fuel elements is significant. In this paper, both of the instrument and method for spherical fuel element wear behavior measurement were studied. In this paper, the DEM numerical simulation method was used to simulation and analyses the measuring wear properties of spherical fuel elements plant, which is very important for optimization of measurement parameters and recommended rotation velocity and Filling quantity of fuel elements numbers. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 1-7; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 6 figs., 1 tab., 18 refs.
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Book
Literature Type
Conference
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Ma Qian; Zhang Weidong
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
AbstractAbstract
[en] The skeleton assembly platform is the key equipment for the manufacture of nuclear fuel assembly. At present, there is no calibration method related to the skeleton assembly platform at home or abroad. In order to ensure the accurate positioning of the frame and the dimension of the skeleton quality, the calibration method of the skeleton assembly platform is carried out. Calibration methods include calibration items, calibration required standard instruments, calibration methods and feasibility analysis of straightness instead of flatness and so on. After the calibration method is determined, the calibration experiment is carried out according to the calibration method. The calibration results are in accordance with the technical requirements, the evaluation uncertainty is also made to prove the calibration method is workable, and it can be extended to assembly platform, pull rods platform and expansion platform, etc. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 15-22; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 7 figs., 6 tabs., 7 refs.
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Book
Literature Type
Conference
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Zheng Ming
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
AbstractAbstract
[en] Test is an important part in the simulator development process, the test phase of the workload, with a lot of repetitive work, need to invest a lot of human resources. In the development of NPP simulator, the demand for test capability of the simulator is becoming more and more urgent. The introduction of automatic testing tools in the development of the simulator can reduce the repetitive work, improve the efficiency and accuracy. In this paper, through the collection of simulator testing process in a variety of automated testing needs, research and development three simulator automated test tools: automatically repeat test tools, steady-state data automatically compare tool, real-time data compare tool. (author)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 23-28; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 8 figs.
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Book
Literature Type
Conference
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AbstractAbstract
[en] This paper describes a kind of sticking strain-gauge process for fuel subassembly guide tube while performing various dynamics experiments for fuel subassembly. Through analyzing the special structure of fuel subassembly strait room and the related assembly process, several process difficulties are introduced, which results from the special structure of fuel subassembly. For getting a solution to these process difficulties, a new method of sticking strain-gauge on the fuel subassembly guide tube and the related process is developed and finally the strain-gauge is successfully stuck on the strait room within the fuel subassembly guide tube. Through experiment and test, this method is verified well and the true and effective data for strain-gauge test is got. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 46-51; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 7 figs., 3 refs.
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Book
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Conference
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AbstractAbstract
[en] Boron carbide powder with its high temperature stability, excellent chemical stability had attracted great attention, and has been widely applied in some fields: Its hardness are next to diamond, and the sample is hard to dissolve, at normal temperature and pressure, boron carbide is difficult to dissolve even if the use of hydrofluoric acid, due to the content of trace elements in the sample number will affect the final performance. In order to accurately measure the impurity content of boron carbide powder, we considered the acid dissolution and alkali dissolution two methods, because the alkali dissolving method will introduce a lot of reagents, and affect the trace element detection in samples, at the same time is hard to completely dissolved the samples, in this paper we used the Acid dissolution method. In order to dissolve boron carbide sample better and faster, through a variety of acids content, types and parameters of the microwave digestion meter instrument working condition test, determined the best dissolved conditions of samples, using microwave digestion meter to dissolve boron carbide samples, then extracting and separating of the B matrix, using ICP-AES method to determine the impurity elements content in the sample. Established the method of measuring impurity elements content in boron carbide powder by ICP-AES. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 41-45; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 6 tabs., 3 refs.
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Book
Literature Type
Conference
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INIS VolumeINIS Volume
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Huang Fan; Yang Tonggao; Qi Shijin; Cao Hui; Yang Donghao
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
AbstractAbstract
[en] The component is the core component in the reactor. The quality of the butt weld between the cladding and the end plug directly affects the service life of the fuel rod and the sale operation of the nuclear power. In order to ensure the quality of butt weld inside the component, X-ray technology is used in the inspection of the casing. According to the structure characteristics of the size of the casing and technical requirements, it is do research on radiographic method, transillumination and process parameters to ensure the process is feasible. Through the process research, it can be successfully found the internal quality inspection method of the butt weld of casing for experiment fast reactor. The following conclusions are drawn: double wall single image transillumination is used in the inspection of experiments fast reactor butt weld of casing and radiograph for every 60°, totally for 6 times, with lead on the film side. Through experiment, the X-ray radiographic parameters for the experiment fast reactor casing of butt weld. And it is well used to ensure welding quality. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 8-14; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 4 figs., 2 tabs., 3 refs.
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Book
Literature Type
Conference
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AbstractAbstract
[en] Uranium fuel is an important part of nuclear reactor. The welding quality of the plug and cladding of the uranium fuel will directly affect the sale operation of the reactor. After the low enrichment of MNSR, the uranium fuel outside diameter is only 5.5 mm and fuel cladding is only 0.5 mm. The fuel needs to work continuously for at least 30 years. Non-destructive testing technology is used in the inspection of MNSR uranium fuel. The paper study the technology of X-ray inspection of weld in uranium fuel. It focused on selecting the appropriate radiography mode calculation the availability radiography area, designing and manufacturing compensation block and exploring the technological parameter. Through technology research, MNSR uranium fuel compensation arrangement and process parameters were determined. The method is applied to the detection of MNSR uranium fuel to ensure the quality of MNSR uranium fuel. (authors)
Primary Subject
Secondary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 29-33; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 7 figs., 1 tab., 3 refs.
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Book
Literature Type
Conference
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Han Fengjiao; Chen Yanhong; Zhang Qingming; Shen Yanan
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.10--Nuclear Measurement and Analysis Society sub-volume2018
AbstractAbstract
[en] In this paper, the determination method of oxygen, nitrogen and carbon content in boron carbide powder were studied respectively by the pulse heating-thermal conductivity method and high frequency induction-thermal conductivity method, the established successfully. The optimum conditions related to sample weighing was confirmed, the type and dosage of fluxing agent was selected, the parameters of the instrument condition was investigated, and the analysis parameters such as power, comparator level, etc. was confirmed. It not only ensure that the sample full approval, but also solved the sample melt collapse problem, reduced the attrition rate of the instrument and improved the stability of the determination results by using tin, nickel basket and graphite power as flux in oxygen and nitrogen content determination. The mixtures of iron, tungsten grain were selected as flux in the determination of carbon content, not only obtained the magnetic permeability, but also ensured the sample fused completely and the accuracy of determination results had been improved. The method established in this study can quickly determine the content of oxygen, nitrogen and carbon content in boron carbide powder thanks to its simple principle, easy operation. The accuracy of this method was about good, the precision better than 5%, and the results was satisfied. The establishment of this method can be developed for boron carbide powder and other process to provide data feedback. (authors)
Primary Subject
Source
Chinese Nuclear Society, Beijing (China); 51 p; ISBN 978-7-5022-8776-4; ; Apr 2018; p. 34-40; 2017 academic annual meeting of China Nuclear Society; Weihai (China); 16-18 Oct 2017; 1 fig., 8 tabs., 6 refs.
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Book
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Conference
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