Zobrazeno 1 - 10
of 2 129
pro vyhledávání: '"Sodium Cooled Fast Reactor"'
Autor:
Byeongyeon Kim, Youngwoong Kim, YunSook Lee, Ki-Ean Nam, Jung Yoon, Yong-Hoon Shin, Hyeonil Kim, Jewhan Lee, BongWan Lee
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 12, Pp 5182-5189 (2024)
This study explores the application of Raman scattering-based optical fiber sensors (OFSs) in extreme environments, specifically focusing on a loop heater vessel with temperatures ranging from 200 °C to 680 °C. This condition generally covers the a
Externí odkaz:
https://doaj.org/article/6508d130c6574e5da67441aaa4a6037f
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1817-1824 (2024)
Based on the design parameters of the core decay heat removal through natural circulation of the typical high-power sodium-cooled fast reactor, using the system analysis program ERAC, a detailed analysis of the reactor core decay heat removal process
Externí odkaz:
https://doaj.org/article/660ab272a06f46ddb7eedd7ab70cabbf
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1859-1865 (2024)
China is accelerating the development of sodium-cooled fast reactor technology. For nuclear reactors, whether it is a pressurized water reactor or a fast reactor, core flow distribution is a key concern, which directly determines whether the reactor
Externí odkaz:
https://doaj.org/article/06bfa23625d042b093c9a8b23a195638
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1884-1892 (2024)
FFTF LOFWOS Test #13 is an unprotected loss of flow test conducted on the FFTF sodium-cooled loop fast reactor in the United States, aimed at demonstrating the inherent safety characteristics of the reactor. To verify advanced neutron science, therma
Externí odkaz:
https://doaj.org/article/b588a2f3db1f4cdcae82a579ef78870f
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1876-1883 (2024)
The cone top cover, as one of the critical pressure boundaries of the fast reactor primary vessel, is crucial for the safe operation of the fast reactor. The structural integrity of the cone top cover is closely related to the temperature load, which
Externí odkaz:
https://doaj.org/article/9360d9e965f64ac8ba4ad4addcdd0a92
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1866-1875 (2024)
Unprotected loss of flow accident is severe for sodium-cooled fast reactor in that it will cause the boiling of sodium and then cause severe accident. For large MOX fuel sodium-cooled fast reactors, the sodium void reactivity is positive, which can m
Externí odkaz:
https://doaj.org/article/9f9d35a13d3646b6911ae9d9d07bec95
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1893-1901 (2024)
The sodium-cooled fast reactor (SFR) not only has the advantages of high coolant temperature, nuclear fuel breeding and nuclear waste transmutation capabilities, but also has the characteristics of good inherent safety. It is one of the fastest-growi
Externí odkaz:
https://doaj.org/article/284a92d0c2b44962b579547e4c3b71b3
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1912-1919 (2024)
Sodium-cooled fast reactor (SFR) is one of the major the Generation Ⅳ nuclear reactors, which utilizes the liquid sodium as the coolant. Despite of the excellent heat-transfer characteristic and low neutron absorption cross-section, the liquid sodi
Externí odkaz:
https://doaj.org/article/5c4174704ac84516a7015daabc0232f1
Publikováno v:
Yuanzineng kexue jishu, Vol 9, Iss 58, Pp 1902-1911 (2024)
The main feature of the sodium-cooled fast reactor (SFR) is the application of liquid sodium as the coolant. Hence, the wetting phenomenon at the solid-liquid interface between stainless steel and liquid sodium is significant in this reactor system.
Externí odkaz:
https://doaj.org/article/fa2bafd2756c452bbdf611e9d7a1c82a
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3626-3643 (2024)
One of the issues in the development of the sodium-cooled fast reactor (SFR) using transuranic (TRU) metallic fuel is the absence of criticality benchmark experiment that faithfully mocks up the nuclear characteristics of the target design for valida
Externí odkaz:
https://doaj.org/article/3aacc65c325543949da763d83f0bee1d