Zobrazeno 1 - 10
of 1 275
pro vyhledávání: '"relap5"'
Autor:
Navid Vahman, Reza Akbari
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3826-3834 (2024)
The main purposes of start-up tests in nuclear power plants (NPPs) are to ensure safe and reliable operation, verify system functionality, comply with regulatory requirements, optimize performance, and establish a foundation for ongoing plant operati
Externí odkaz:
https://doaj.org/article/844b093cbc2d40f1994c63f6c0f00e96
Publikováno v:
Energies, Vol 17, Iss 22, p 5777 (2024)
The RELAP5 code is a computational tool designed for transient simulations of light water reactor coolant systems under hypothesized accident conditions. The original wall drag partition model in the RELAP5 code has a problem in that the bubble veloc
Externí odkaz:
https://doaj.org/article/d6fbc95355b24de0ba676134b38759ac
Autor:
Geng Yiwa, Liu Xiongbin, Li Ziyi, Huang Shuliang, Zhou Lanyu, Xue Yanfang, Li Xiaotian, Zhang Yajun
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
NHR-200-II is a small integrated pressurized water reactor with 200 MW core thermal power. The core heat is transferred to two independent intermediate circuits via fourteen in-vessel primary heat exchangers (PHE), and the heat in the intermediate ci
Externí odkaz:
https://doaj.org/article/ca74f91dec0c4d95bf60f4260ca6522c
Publikováno v:
Journal of Applied Fluid Mechanics, Vol 16, Iss 12, Pp 2529-2539 (2023)
Feedwater leakages due to excessive loads and cracking caused by corrosion or fatigue failure can affect the reliability of the production facilities. In the present work, a numerical study of a small leakage accident type SB-LOCA on the feed water p
Externí odkaz:
https://doaj.org/article/5f84d2318ee943c4979f5443e8c7fde8
Analysis of loss of cooling accident in VVER-1000/V446 spent fuel pool using RELAP5 and MELCOR codes
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 8, Pp 3102-3113 (2023)
Following the Fukushima nuclear disaster, the simulation of accidents in the spent fuel pool has become more noticeable. Despite the low amount of decay heat power, the consequences of the accidents in a spent fuel pool (SFP) can be severe due to the
Externí odkaz:
https://doaj.org/article/8e59b7bad11b42029aabe4988dc6f5e8
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 6, Pp 1205-1214 (2023)
Compared with traditional large scale pressurized water reactor, the volume of the containment of small pressurized water reactor is small. During a loss of coolant accident (LOCA), the containment pressure of small pressurized water reactor rises ra
Externí odkaz:
https://doaj.org/article/d3658691a95c439e97e0e727edd4c827
Autor:
A.K. Trivedi, D.R. Novog
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 4, Pp 1448-1459 (2023)
A key element of the safety analysis is Loss of Coolant Analysis (LOCA) which must be performed using system thermal-hydraulic codes. These codes are extensively validated against separate effect and integral experiments.RELAP/SCDAPSIM is one such co
Externí odkaz:
https://doaj.org/article/3a31bf4a945540e9b603f6406bd3a01a
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 2, Pp 313-320 (2023)
RELAP5 is one of the most commonly used programs for reactor thermal hydraulic analysis. Due to the early developing time, RELAP5 does not have a friendly graphical user interface and interactive interface, resulting in the lack of human-computer int
Externí odkaz:
https://doaj.org/article/891e885ac49142f783aa90860eba9f6e
Autor:
Tae Beom Lee, Yong Hoon Jeong
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4776-4797 (2022)
In the one-dimensional thermal-hydraulic (TH) codes, a subcooled boiling model to predict the void fraction profiles in a vertical channel consists of wall heat flux partitioning, the vapor condensation rate, the bubbly-to-slug flow transition criter
Externí odkaz:
https://doaj.org/article/e62e1910c4aa42e2bf74b4e58aceb3bc
Publikováno v:
He jishu, Vol 47, Iss 3, Pp 030602-030602 (2024)
BackgroundPassive residual heat-removal system (PRHRS) based on natural circulation has been widely used in small reactors connected on secondary side loop.PurposeThis study aims to develop and analyze a passive residual heat-removal system on the se
Externí odkaz:
https://doaj.org/article/2a1ebe4f1b184ea49473d8560b98f42b