Zobrazeno 1 - 10
of 467
pro vyhledávání: '"Lead-cooled fast reactor"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3286-3297 (2024)
Traditional text-based system engineering, which has been used in the design and application of passive residual heat removal system (PRHRS) for lead-cooled fast reactors, is prone to several problems such as low development efficiency, long iteratio
Externí odkaz:
https://doaj.org/article/12a27f822a6041c69e4b7cde226dfbc8
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 6, Pp 2332-2342 (2024)
Lead-cooled fast reactors (LFRs) have a wide range of application scenarios, which require the thermal-hydraulic characteristics of LFRs to be reliable. In the present paper, the Lead-cooled fast reactor Thermal-Hydraulic Analysis Code LETHAC was dev
Externí odkaz:
https://doaj.org/article/076a9c9d45344d32976f811eea83be3c
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss 4, Pp 814-824 (2024)
Miniaturization of nuclear energy systems will be a promising direction for nuclear industry development in the future, in which micro lead-cooled fast reactors (LFRs) are a type of technical route in relevant. During the R&D of micro LFRs, transient
Externí odkaz:
https://doaj.org/article/73cfcb960e634d24b008b91544d0cffa
Autor:
Jonathan Hawes, Jordan Knapp, Robert Burrows, Robert Montague, Paul Wilcox, Hual-Te Chien, Jeff Arndt, Steve Walters
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 4, Pp 1460-1471 (2024)
2D and 3D ultrasonic imaging has so far not been demonstrated in pure molten lead in the open literature. In this study the development of such an ultrasonic device for imaging is outlined and results from testing at 380 °C in lead are presented. Th
Externí odkaz:
https://doaj.org/article/98b6dcd27e2940cd907a2e01b328b411
Publikováno v:
Yuanzineng kexue jishu, Vol 58, Iss 2, Pp 372-381 (2024)
Lead-cooled fast reactor (LFR) is one of six advanced nuclear energy systems recommended by Gen-4 International Forum. With the significant development in materials and equipment, LFR is more and more closed to engineering applications. Right now, pl
Externí odkaz:
https://doaj.org/article/d81e373e570a48aca7acbbb136611c72
Publikováno v:
Journal of Nuclear Engineering, Vol 5, Iss 1, Pp 1-12 (2023)
The accurate calculation of reactor core heating is vital for the design and safety analysis of reactor physics. However, negative KERMA factors may be produced when processing and evaluating libraries of the nuclear data files ENDF/B-VII.1 and ENDF/
Externí odkaz:
https://doaj.org/article/bfc92d312d634df4b16de712f2a82d80
Publikováno v:
He jishu, Vol 47, Iss 4, Pp 040602-040602 (2024)
BackgroundTraditional text-based system engineering in the design and application of passive residual heat removal systems (PRHRS) for lead-cooled fast reactors has several requirement problems, such as low development efficiency, a long iteration cy
Externí odkaz:
https://doaj.org/article/8329ffc260e24847a4765d313244c27e
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