Zobrazeno 1 - 10
of 520
pro vyhledávání: '"steam generator tube"'
Autor:
Xiaomeng LI, Lin YANG
Publikováno v:
南方能源建设, Vol 11, Iss 6, Pp 94-101 (2024)
[Introduction] Under the scouring impact of secondary side fluid, the steam generator tube is prone to flow-induced vibration. One of the main mechanisms leading to tube vibration is the random turbulent force. When the fluctuating pressure frequency
Externí odkaz:
https://doaj.org/article/33f99161c9644be9981adcfb89e88044
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 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:
Yuanzineng kexue jishu, Vol 57, Iss 7, Pp 1406-1415 (2023)
The LBE-cooled reactor is one of the important choices for sustainable and safe development of nuclear energy systems in the future. The safety issues involved with the steam generator tube rupture (SGTR) accident must be considered in the design and
Externí odkaz:
https://doaj.org/article/eacdcb22b02641e2a222ca721e4c6eef
Autor:
Kenichi KURISAKA
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00377-23-00377 (2023)
This study aims to understand the time-dependent change in the occurrence rate of leak from steam generator (SG) tubes in sodium-cooled fast reactors (SFRs). The target SFRs in the present paper are Phenix in France and BN-600 in Russia. By reviewing
Externí odkaz:
https://doaj.org/article/b9641d6281d647f4b818177b61044b76
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Publikováno v:
Journal of Materials Research and Technology, Vol 20, Iss , Pp 2527-2541 (2022)
The purpose of this study is to elucidate the effect of a film forming amine (FFA) on the magnetite deposition behavior of Alloy 690 tube in the secondary coolant system of pressurized water reactors. By the addition of octadecylamine (ODA), which is
Externí odkaz:
https://doaj.org/article/913acdc299d74359a550638c329edcf8
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 7, Pp 2702-2713 (2022)
A steam generator tube rupture accompanying a core damage may cause the fission product to be released to environment bypassing the containment. In such an accident, the steam generator is the major path of the radioactive aerosol release.AEOLUS faci
Externí odkaz:
https://doaj.org/article/f3802095922143ccb1f6a4f2ef8dcf6e
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 5, Pp 1570-1578 (2022)
During a severe accident, steam generator (SG) tubes undergo rapid changes in the pressure and temperature. Therefore, an appropriate creep model to predict a short term creep damage is essential. In this paper, a novel creep model for Alloy 690 SG t
Externí odkaz:
https://doaj.org/article/0d455e571dee4fd5983218846d6b2bae