Zobrazeno 1 - 10
of 144
pro vyhledávání: '"relap5 code"'
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
Akademický článek
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Publikováno v:
مجله علوم و فنون هستهای, Vol 43, Iss 2, Pp 114-124 (2022)
The purpose of this paper is to investigate the possibility of using tubular fuel assemblies in Tehran Research Reactor (TRR) from the thermal hydraulic perspective. Tubular fuels have been used successfully in many Russian model research reactors in
Externí odkaz:
https://doaj.org/article/148384ec6c634ae79f9989f15dfc7db9
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 9, Iss 2B (2021)
The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Acc
Externí odkaz:
https://doaj.org/article/f4308523d7684e298ff8d38ee815dd46
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
Motivated by the significant natural circulation capability of lead–bismuth eutectic (LBE)–cooled systems, the RELAP5 MOD3.2 code was modified for the analysis of LBE-cooled reactors and non-nuclear systems. The thermo-physical properties of LBE
Externí odkaz:
https://doaj.org/article/cdb5aace31e6455b85ddc2319af70030
Autor:
A.R. Antariksawan, S. Widodo, M. Juarsa, S. Ismarwanti, D. Saptoadi, M.H. Kusuma, T. Ardiyati, T. M.I. Mahlia
Publikováno v:
Atom Indonesia, Vol 45, Iss 1, Pp 17-25 (2019)
In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident. An example is the applic
Externí odkaz:
https://doaj.org/article/50399aadaf404fbb82a4ae19c9606471
Publikováno v:
Frontiers in Energy Research, Vol 8 (2020)
Laminar-turbulent transition flow can be observed in thermal engineering applications, but the flow resistance and heat transfer characteristics are not fully understood. In this work, flow and heat transfer for the laminar-turbulent transition in a
Externí odkaz:
https://doaj.org/article/5826ff312c1b4425a37480b6a4d62554
Experimental and Numerical Results of LIFUS5/Mod3 Series E Test on In-Box LOCA Transient for WCLL-BB
Autor:
Marica Eboli, Francesco Galleni, Nicola Forgione, Nicolò Badodi, Antonio Cammi, Alessandro Del Nevo
Publikováno v:
Energies, Vol 14, Iss 24, p 8527 (2021)
The in-box LOCA (Loss of Coolant Accident) represents a major safety concern to be addressed in the design of the WCLL-BB (water-cooled lead-lithium breeding blanket). Research activities are ongoing to master the phenomena and processes that occur d
Externí odkaz:
https://doaj.org/article/01b46ea0c7524942a2747686beb0a076
Autor:
Takeshi Takeda, Iwao Ohtsu
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 5, Pp 928-940 (2017)
An experiment using the Primӓrkreislӓufe Versuchsanlage (PKL) was performed for the OECD/NEA PKL-3 Project as a counterpart to a previous test with the large-scale test facility (LSTF) on a cold leg small-break loss-of-coolant accident with an acci
Externí odkaz:
https://doaj.org/article/1ed088c043324cfd9b994c256badef91
Autor:
A.S. Ekariansyah, S. Widodo
Publikováno v:
Atom Indonesia, Vol 42, Iss 2, Pp 79-88 (2016)
Generation II Nuclear Power Plants (NPPs) have a design weakness as shown by the Fukushima accident. Therefore, Generation III+ NPPs are developed with focus on improvements of fuel technology and thermal efficiency, standardized design, and the use
Externí odkaz:
https://doaj.org/article/8fc05e32ff6f4608a2bde22fa613f3c4