Zobrazeno 1 - 10
of 2 162
pro vyhledávání: '"loss of coolant accident"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2375-2387 (2024)
The passive safety systems (PSSs) within water-cooled reactors are meticulously engineered to function autonomously, requiring no external power source or manual intervention. They depend exclusively on inherent natural forces and the fundamental pri
Externí odkaz:
https://doaj.org/article/865db41b5b2d4cf6b8e238f031fc4f6f
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 7, Pp 2438-2446 (2023)
To cool down a nuclear reactor core and prevent the fuel damage without a pump-driven active component during any anticipated accident, the passive emergency core cooling system (PECCS) was designed and adopted in an advanced light water reactor, i-P
Externí odkaz:
https://doaj.org/article/3153f1a970cb47dc9b3600ac3b6bdf9b
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 9, Pp 1699-1705 (2023)
Due to the weak moderating capability of carbon dioxide itself, supercritical carbon dioxide cooled reactor typically has a hard energy spectrum and is susceptible to safety issues introduced by positive reactivity feedback in the event of LOCA (loss
Externí odkaz:
https://doaj.org/article/98a05b0404de4f9f96c5235f51a959d4
Publikováno v:
Frontiers in Nuclear Engineering, Vol 3 (2024)
Introduction: The accurate prognosis of reactor accidents is essential for deploying effective strategies that prevent radioactive releases. However, research in the nuclear sector is limited. This paper introduces a novel Temporal Fusion Transformer
Externí odkaz:
https://doaj.org/article/e2b42f83797d422686a81c3375a30482
Autor:
Keferson Almeida Carvalho, Graiciany de Paula Barros, Vanderley de Vasconcelos, Andre Augusto Campagnole dos Santos
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 12, Iss 1 (2024)
This study presents a framework merging failure mode and effect analysis (FMEA) and fault tree analysis (FTA) techniques to evaluate loss of coolant accident (LOCA) in the Brazilian Reactor TRIGA IPR-RI. At first, FMEA identified failure modes and pr
Externí odkaz:
https://doaj.org/article/77fc94479c5f4597ad86218acb1a23c6
Autor:
Anatoly N. Shmelev, Nikolay I. Geraskin, Vladimir A. Apse, Vasily B. Glebov, Evgeny G. Kulikov, Andrey A. Krasnoborodko
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 2, Pp 412-420 (2023)
This paper presents the results obtained from numerical evaluations for the possibility of large-scale 238Pu production in the light-water VVER-1000 reactor and the reactivity effect caused by the loss-of-coolant accident in the central fuel assembly
Externí odkaz:
https://doaj.org/article/738038d8b3914ed7a5989622406aa895
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00474-23-00474 (2023)
Loss Of Coolant Accident causes the propagation of a transient rarefaction wave within the primary circuit that generates a transient pressure load on the baffle surrounding the reactor core. This is the result of nonidentical travel times of the rar
Externí odkaz:
https://doaj.org/article/8dd5d0fdb20f48619116f293774864da
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00416-23-00416 (2023)
In the framework of the development of fusion energy, one of the most prominent technologies arising to address the issues of tritium breeding and power conversion is the Water-Cooled Lithium-Lead (WCLL). This technology utilizes a molten eutectic al
Externí odkaz:
https://doaj.org/article/a366978355f84aa89aadd5861e364d93
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