Zobrazeno 1 - 10
of 7 959
pro vyhledávání: '"steam generator"'
Autor:
CHEN Yutong1, , ZHANG Dalin1, , LIN Yue1, ZHANG Xisi2, TIAN Wenxi1, QIU Suizheng1, SU Guanghui
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss S1, Pp 16-32 (2024)
Steam generator tube rupture (SGTR) accident is one of the accident scenarios that must be considered during the design and safety analysis process of lead-cooled fast reactors (LFR). Focused on this topic, numerous experiments and theoretical resear
Externí odkaz:
https://doaj.org/article/27e56ff6d34e418fab228faf0df36911
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 7, Pp 2718-2731 (2024)
To ensure the operational safety of nuclear power plants, we present a Quadruped Inspection Robot that can be used for many types of steam generators. Since the Inspection Robot relies on the Holding Modules to grip the tube-sheet, it can be regarded
Externí odkaz:
https://doaj.org/article/c84a0d1aab08468789c240e3c806a3e8
Publikováno v:
SolarPACES Conference Proceedings, Vol 2 (2024)
High-temperature steam is essential for operating solid oxide electrolysis cells (SOEC). This paper demonstrated a new type of high-temperature solar steam generator that uses ceramic foam as a porous absorber. Water is sprayed into the porous absorb
Externí odkaz:
https://doaj.org/article/9469687beb954b7989dbd78bccaddecd
Autor:
Hooton, Brian, author
Publikováno v:
Understanding Nuclear Reactors : Global Warming and the Hydrogen Strategy, 2024, ill.
Externí odkaz:
https://doi.org/10.1093/oso/9780198902652.003.0007
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1513-1525 (2024)
An improved mitigation system for thermally-induced steam generator tube rupture accidents was introduced to prevent direct environmental release of fission products bypassing the containment in the OPR1000. This involves injecting bypassed steam int
Externí odkaz:
https://doaj.org/article/edc328cd45554094abb0b0a48ef0df1f
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 6, Iss 1, Pp 32-42 (2024)
The advantages of the helically coiled tube steam generator lie not only in its high heat transfer efficiency but also in its compact structure, which is initially used in Pb–Bi–SCO2 reactors, and its main function is to transfer the heat from th
Externí odkaz:
https://doaj.org/article/e2318136a74e47129f0bfba257defab8
Autor:
Tomohiko Yamamoto, Atsushi Kato, Masato Hayakawa, Kazuhito Shimoyama, Kuniaki Ara, Nozomu Hatakeyama, Kanau Yamauchi, Yuhei Eda, Masahiro Yui
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 893-899 (2024)
In a secondary cooling system of a sodium-cooled fast reactor (SFR), rapid detection of hydrogen due to sodium-water reaction (SWR) caused by water leakage from a heat exchanger tube of a steam generator (SG) is important in terms of safety and prope
Externí odkaz:
https://doaj.org/article/687ef101b1b34ed29511af02d53f54f9
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Pp 328-336 (2024)
The sodium-heated once-through steam generator (OTSG) plays an important role in separating the second and third circuits of sodium cooled fast reactor (SFR). Once the heat transfer pipe breaks, it will cause serious sodium water reaction, which will
Externí odkaz:
https://doaj.org/article/9f417f57d31146fd95ca4add26f4358a
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 1, Pp 257-264 (2024)
The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, w
Externí odkaz:
https://doaj.org/article/284cb6578d2f4990ab857c52f70d7342
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4561-4569 (2023)
A correct understanding of vibration-based degradation is crucial from the standpoint of maintenance for Steam Generators (SG) as crucial mechanical equipment in nuclear power plants. This study has established a novel approach to developing a model
Externí odkaz:
https://doaj.org/article/956601bae12a4eef9350a37c1a3138e5