Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Yousen Hu"'
Autor:
Min Rui, Tianming Chen, Mingjia Zhou, Xiong Zheng, Yisong Hu, Desheng Jin, Yousen Hu, Yulong Mao
Publikováno v:
Frontiers in Energy Research, Vol 11 (2023)
Helical tubes are widely used in nuclear plants, heat recovery process, refrigeration technology, etc. It is obtained the helical tubes dry out point prediction model in accordance with the experimental conditions by numerical simulation. The article
Externí odkaz:
https://doaj.org/article/6352582eb5fe4a809608bcea65095b28
Publikováno v:
Frontiers in Energy Research, Vol 11 (2023)
Helical tubes are widely used in nuclear plants, heat recovery process, and refrigeration technology. The fluid is influenced by centrifugal force flow through the helical tube, accompanied by secondary flow which is conducive to the enhancement of h
Externí odkaz:
https://doaj.org/article/b51350fb852943869144bdd3bb8ec91b
Autor:
Jiapeng Liao, Yousen Hu, Jinggang Li, Desheng Jin, Shuqi Meng, Tianming Ruan, Yisong Hu, Ziyu Zhang
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 3, Pp 984-990 (2022)
Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn inject
Externí odkaz:
https://doaj.org/article/00a8e76957834304958e2f2fefbce2db
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
In order to reveal the effect of thermal hydraulic conditions on the PWR CIPS risk, the evaluation of a PWR CIPS risk in the first cycle under different core flow rates, average primary temperatures, power levels, and primary pressures was conducted
Externí odkaz:
https://doaj.org/article/59d5e0c9a5154e3faf222e4e6ed9d07d
Akademický článek
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Autor:
Yisong Hu, Shuqi Meng, Tianming Ruan, Yousen Hu, Desheng Jin, Jiapeng Liao, Ziyu Zhang, Jinggang Li
Publikováno v:
Nuclear Engineering and Technology. 54:984-990
Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn inject
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::473c3c799ecd37940eb77c8264987757
https://doi.org/10.1016/j.net.2021.09.009
https://doi.org/10.1016/j.net.2021.09.009
Publikováno v:
Springer Proceedings in Physics ISBN: 9789819910229
CPR1000 nuclear power plants have the risk of reactor trip during the house load and turbine trip transients. Rapid power reduction system of AP1000 nuclear power plants and fast power setback system for VVER nuclear power plants are designed respect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2e224afe51bcbd5867d6908f64ce3e9a
https://doi.org/10.1007/978-981-99-1023-6_16
https://doi.org/10.1007/978-981-99-1023-6_16
Publikováno v:
Springer Proceedings in Physics ISBN: 9789819910229
During the normal operation of a pressurized water reactor plant, RPN430KA (quadrant power tilt rate over 3%) alarms were issued several times, and the alarm frequency increased with the increase of burnup, which affected the normal operation of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5e3e36f4954c35986a131a95aa176d0b
https://doi.org/10.1007/978-981-99-1023-6_40
https://doi.org/10.1007/978-981-99-1023-6_40
Publikováno v:
Volume 8: Computational Fluid Dynamics (CFD) and Applications.
As key nuclear equipment, once-through steam generator (OTSG) can guarantee the safe operation of nuclear power plants. The accurate calculation of the OTSG’s pressure drop is particularly critical to the design of the nuclear power plant primary c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ea340e9478f66eeb608eebc80dabb364
https://doi.org/10.1115/icone29-89095
https://doi.org/10.1115/icone29-89095