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AbstractAbstract
[en] This issue is the collection of 603 papers presented at the entitled meetings. All the presented papers are indexed individually. (J.P.N.)
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May 2019; [4028 p.]; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format
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Stakenborghs, Robert
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] This paper presents the derivation of a closed form solution for density driven natural circulation flows (i.e. – thermosiphon) in a thermal system typical of power plants. The assumptions and methodology to properly define the mathematical system are described and an example provided. The solution is shown for a common power plant system. (author)
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Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 7 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track01, Paper ID: ICONE27-2274F.pdf; 11 refs., 5 figs.
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Lin Daping; Huang Xiaoyun
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] The rupture of pipe within acid or alkali medium in some third-generation nuclear station will cause fluid spray, which will threaten the safety related equipment nearby. The rupture position and spray region can be calculated via method introduced in ANS58.2. Measures are taken when piping rupture will cause serious influence on the safety related items, to protect the safety of nuclear station. (author)
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Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 4 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track03, Paper ID: ICONE27-1388F.pdf; 2 refs., 6 figs., 1 tab.
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Liu Changliang; He Wenhong
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] From the perspective of system, the Flowmaster model of the reactor coolant system is combined with the CFD model of the surge line. The transient simulation of the reactor coolant system is to obtain the fluctuation of temperature and pressure at the boundary of the surge line with time, and then the results serve as the input conditions to the surge line CFD model, the flow, temperature and pressure in the surge line are calculated with the distribution of space and time. This kind of combined simulation is used to find the reason of temperature fluctuation of surge line, to explore its law and to provide the basis for the design of nuclear pipeline. (author)
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Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 4 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track08, Paper ID: ICONE27-1883F.pdf; 3 refs., 16 figs.
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Xie Zhaoyang; Song Yushou
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] Methods for localizing radiation sources are frequently used in decontamination of the nuclear facilities. In this study, a localization method based on stereo vision was came up with. The pinhole Gamma camera was utilized to project the radiation source into images. Projections’ location in each image was used to construct relations between the three-dimensional source and two-dimensional projections. The three-dimensional location of the source was estimated using least mean squares. Performance of the method was studied with effects of precision and accuracy on the projections. Results showed that the localization method was able to estimate correctly under the situation of precision but failed while accuracy occurred. (author)
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Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 5 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track10, Paper ID: ICONE27-1870F.pdf; 8 refs., 5 figs.
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AbstractAbstract
[en] Waste minimization of air filter generated from nuclear power plant can be realized by clearance and design of new recyclable structure. The metal framework can get clearance by several steps to reduce the waste volume. According to some framework clearance of scrap air filter, we put forward some improvement suggestions on the air filter structure. So that the framework can be easily dismantled, secondary contamination can be avoided. Waste minimization goal can be further achieved by reuse of the outside metal framework. (author)
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Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 4 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track10, Paper ID: ICONE27-1171F.pdf; 3 refs., 3 figs., 6 tabs.
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ADSORBENTS, CARBON, CLEANING, ELEMENTS, EQUIPMENT, FILTERS, HALOGENS, ISOTOPES, MANAGEMENT, NONMETALS, NUCLEAR FACILITIES, OPTIMIZATION, PARTICLES, POLLUTION CONTROL EQUIPMENT, POWER PLANTS, PROCESSING, RADIATIONS, RADIOACTIVE WASTE MANAGEMENT, THERMAL POWER PLANTS, WASTE MANAGEMENT, WASTE PROCESSING
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Peng Binsen; Xia Hong; Yang Bo; Zhu Shaomin
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] The nuclear power plant is a complex, non-linear and highly dynamic system, composed of many devices, functional requirements. A reliable condition monitoring technology is one of the important means to improve its safety. The traditional threshold-based condition monitoring method has many shortcomings in practicality. According to the actual situation, the normal operation data is of large amount, and the abnormal data is little. In this paper, a new condition monitoring method based on isolation forest algorithm is proposed to solve this problem and the simulation proves that the proposed method can quickly and accurately identify the condition of the system. (author)
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Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 7 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track06, Paper ID: ICONE27-1400F.pdf; 7 refs., 4 figs., 3 tabs.
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Chen, Shi; Demachi, Kazuyuki
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] An urgent lesson learned from Fukushima Daiichi accident is what can happen by natural disaster also can be made to happen by human design. The accident raised a fear that terrorists could cause a similar accident by acts of sabotage against nuclear facilities and it is noticeable that threats of nuclear terrorism for nuclear security is increased after the accident. Especially as a threat to nuclear facilities, insider sabotage is worthy of attention. In this paper, we present an insider sabotage detection method in response to the certain limitations of PPS in nuclear facilities, which focus on hand motion recognition using Deep Learning. (author)
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Source
Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 7 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track16, Paper ID: ICONE27-1478F.pdf; 16 refs., 8 figs., 1 tab.
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Cheng Pengxin; Gui Nan; Yang Xingtuan; Tu Jiyuan; Jia Haijun
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] Helical pipes have been extensively adopted in industries and engineering, especially in nuclear power plants as steam generators. Compared with straight ones, helical pipes gain the advantage of improved heat transfer efficiency but face the challenge of adverse pressure resistance. In this paper we utilized the innovative Lattice Boltzmann Method to investigate the flow characteristics in helical pipes. The results proved in good accordance with previous experiments and could provide assistance for the design and optimization of helical pipes. (author)
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Source
Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 7 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track09, Paper ID: ICONE27-1503F.pdf; 11 refs., 15 figs., 3 tabs.
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Zhang Jiemin; Ji Yunzhe; Lin Hongtao; Xue Na; Liu Xinjian; Qiu Lin
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)2019
AbstractAbstract
[en] Based on the analysis of the key issues affecting the emergency evacuation time of the nuclear power plant site. The site emergency evacuation simulation program SEES is compiled to estimate the emergency evacuation time of the site, and the sensitivity of parameters is further analyzed. The research results show that during the emergency evacuation of the nuclear power plant site, the departure interval of public vehicles is the main influencing factor. The setting of the emergency rendezvous point in the site will obviously affect the hidden efficiency of the personnel, compared with the impact on the evacuation time. The impact of the speed of movement of people and vehicles is relatively minimal. (author)
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Source
Japan Society of Mechanical Engineers, Tokyo (Japan); [4028 p.]; May 2019; 6 p; ICONE-27: 27. international conference on nuclear engineering; Tsukuba, Ibaraki (Japan); 19-24 May 2019; Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo, 160-0016 Japan; Available as Internet Data in PDF format, Folder Name: Track12, Paper ID: ICONE27-1501F.pdf; 7 refs., 9 figs.
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