Zobrazeno 1 - 10
of 134
pro vyhledávání: '"OTSG"'
Autor:
Keon Yeop Kim, Young Suk Bang
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3315-3329 (2024)
Small Modular Reactors (SMRs) adopt the Helically Coiled Once-Through Steam Generators (OTSG) extensively for its compactness and higher heat transfer efficiency. As a heat exchanger between the primary side (reactor coolant system) and the secondary
Externí odkaz:
https://doaj.org/article/f3e50739a82140849e381c7fbfe6e87b
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 4, Pp 189-199 (2023)
When there are two sets of parallel once through-steam generators(OTSG) in the natural circulation loop, the thermal-hydraulic characteristics are complicated. Flow instability often occurs in such loops. In order to alleviate the harm caused by flow
Externí odkaz:
https://doaj.org/article/4d6d34a693a8451ea992059b51d3ebb1
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
Externí odkaz:
https://doaj.org/article/4d336b69b64245de9796b79889e05ecf
Autor:
Xianghui Lu, Xin Wang, Xiong Zheng, Xiting Chen, Shuqi Meng, Tianming Ruan, Jun Chen, Yulong Mao, Yisong Hu, Chaohao Shang
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
Introduction: A simulation model was developed by coupling a one-dimensional (1D) system code and 3D CFD software, to analyze the three-dimensional (3D) flow and heat transfer characteristics of the once-through steam generator (OTSG).Methods: The sh
Externí odkaz:
https://doaj.org/article/eac1456686314c008545fd45d18abe18
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
The flow characteristics of the primary side of the helical coil once-through steam generator (OTSG) have a significant impact on the safe operation of the reactor. Different from the land-based stationary working conditions, the flow of the primary
Externí odkaz:
https://doaj.org/article/31a8565cc87047b6ac8c05ad41c95a08
Autor:
Mao Yulong, Meng Shuqi, Lu Xianghui, Jin Desheng, Wang Xiaoting, Li Kejia, Hu Yisong, Hu Yousen, Rui Min
Publikováno v:
Frontiers in Energy Research, Vol 11 (2023)
During the power operation of nuclear reactors, the corrosion products in the secondary circuit will deposit on the inside of Helical-coiled One-Through Steam Generator (H-OTSG) heat transfer tubes and form fouling. The main component of fouling is i
Externí odkaz:
https://doaj.org/article/afee43b7edc643cab54b6a73797c87ef
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
Akademický článek
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Akademický článek
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Autor:
Juhyeon Yoon
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 11, Pp 3643-3652 (2021)
Sizing the tube inlet orifice of a Once-Through Steam Generator (OTSG) is important to protect the integrity of the tubes from thermal cycling and vibration wear. In this study, a new sizing criterion is proposed for the tube inlet orifice to suppres
Externí odkaz:
https://doaj.org/article/6b96c60baf4c442989363a61e8dc467c