Zobrazeno 1 - 10
of 70
pro vyhledávání: '"PGSFR"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 2, Pp 359-374 (2024)
A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs). The MARS-LMR code, system transient s
Externí odkaz:
https://doaj.org/article/0654ccae3b13466e83ab215991998039
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 1, Pp 353-363 (2023)
The STELLA-2 is a large-scale sodium thermal-hydraulic integral effect test facility and supports the development of PGSFR. The facility adopted Pump Simulation Loop System (PSLS) concept for the mechanical sodium pump in the reference reactor to con
Externí odkaz:
https://doaj.org/article/6d0a170d57084ea5915ac3739b44dfc6
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4125-4133 (2022)
KAERI (Korea Atomic Energy Research Institute) developed the conceptual design of PGSFR (Prototype Gen-IV Sodium Cooled Fast Reactor) and Burner Reactor. Since the reactor characteristics of the PGSFR and Burner Reactor are different, the shape, size
Externí odkaz:
https://doaj.org/article/a4ec6eaa66024398a89a96fc4cb97cfa
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 9, Pp 3551-3566 (2022)
The STELLA program was launched to support the PGSFR development in 2012 and for the 2nd stage, the STELLA-2 facility was designed to investigate the integral effect of safety systems including the comprehensive interaction among PHTS, IHTS and DHRS.
Externí odkaz:
https://doaj.org/article/99f7be96fbfa4ca69a69854fbf66f9e1
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 5, Pp 1580-1586 (2021)
The application of induction bending processes to industrial pipe production is increasing. The induction bending process has the effect of reducing the number of inspections and preventing leaks by reducing the weld of the pipe. For these reasons, e
Externí odkaz:
https://doaj.org/article/be848ae500ba4b0f93fa58f171e35c6c
Autor:
Jaesik Kwak, Hee Reyoung Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 5, Pp 1429-1435 (2021)
The temperature distribution of an electromagnetic pump was analyzed with a flow rate of 1380 L/min and a pressure of 4 bar designed for the sodium thermo-hydraulic test in the Sodium Test Loop for Safety Simulation and Assessment-Phase 1 (STELLA-1).
Externí odkaz:
https://doaj.org/article/8aeceb52c4d0487ea47bd79bf38bccfd
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 4, Pp 1109-1118 (2021)
The construction of STELLA-2 facility is on-going to demonstrate the safety system of PGSFR and to provide comprehensive understanding of transient behavior under DBEs. Considering that most events are single-phase natural circulation flow with slow
Externí odkaz:
https://doaj.org/article/26dc140d634d4361a904405ea7d16f9b
Autor:
Jaesik Kwak, Hee Reyoung Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 7, Pp 1380-1385 (2020)
An annular linear induction electromagnetic pump (ALIP) which has a developed pressure of 0.76 bar and a flow rate of 100 L/min is designed to analysis end effect which is main problem to use ALIP in thermohydraulic system of the prototype generation
Externí odkaz:
https://doaj.org/article/321003955af84cedbbcfe1df610f5be8
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Akademický článek
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