Zobrazeno 1 - 10
of 32
pro vyhledávání: '"Huasong Cao"'
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
A combination of Convolutional Neural Network (CNN), Long-Short Term Memory (LSTM), and Convolutional LSTM (ConvLSTM) is constructed in this work for the fault diagnosis and post-accident prediction for Loss of Coolant Accidents (LOCAs) in Nuclear Po
Externí odkaz:
https://doaj.org/article/af3d6f557ebd488dad20438cc61a6c1a
Publikováno v:
Progress in Nuclear Energy. 159:104631
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3a432df479defaf39dc22da3fa55dbc9
https://doi.org/10.1016/j.pnucene.2023.104631
https://doi.org/10.1016/j.pnucene.2023.104631
Publikováno v:
Volume 4: Student Paper Competition.
A pressure wave propagation across the second loop of a sodium-cooled fast reactor may lead to severe damage to the pipes and the equipment due to a large leakage sodium-water reaction accident. Therefore, the pressure source and the pressure wave pr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5deedaef40d09a3b00c2d328ffac40fd
https://doi.org/10.1115/icone28-64490
https://doi.org/10.1115/icone28-64490
Publikováno v:
Volume 4: Student Paper Competition.
The steam generator of the sodium-cooled reactor is the barrier between the secondary and third loops. When the heat transfer pipe breaks, the water/steam will pour into the sodium and a sodium-water reaction will occur. The pressure in the secondary
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9fbb46c7359e8ae6e5ea0cb979462969
https://doi.org/10.1115/icone28-64454
https://doi.org/10.1115/icone28-64454
Publikováno v:
Annals of Nuclear Energy. 171:109036
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::550ab62e924eae209168851f848e9205
https://doi.org/10.1016/j.anucene.2022.109036
https://doi.org/10.1016/j.anucene.2022.109036
Publikováno v:
Progress in Nuclear Energy. 142:104010
A sodium-cooled fast reactor (SFR) is one of Generation IV nuclear systems. The once-through steam generator is important for heat transfer and acts as a barrier to separate the sodium and water. If the heat transfer tube breaks, a sodium–water rea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68fb25e239585bd036cdc1d6d8f319c7
https://doi.org/10.1016/j.pnucene.2021.104010
https://doi.org/10.1016/j.pnucene.2021.104010
Publikováno v:
Annals of Nuclear Energy. 154:108147
Frequent and wide-range load changes in small pressurized water reactors applied for nuclear-powered devices are necessary under complex and harsh conditions. However, the traditional power regulation method does not consider the stroke of the contro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::227283ea35a5c384efe028d1fcc61d8d
https://doi.org/10.1016/j.anucene.2021.108147
https://doi.org/10.1016/j.anucene.2021.108147
Autor:
Huasong Cao
Publikováno v:
Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management.
Lots of efforts have been made to Research & Development of Small pressurized water reactors (SPWRs). Steam generator tube break occurs due to wear and corrosion frequently in the reactor. Among the breaks, Small Steam Generator Tube Break (SSGTB) is
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f9912d96dc916f3dc3fd727e6995a5f6
https://doi.org/10.1115/icone25-66637
https://doi.org/10.1115/icone25-66637
Publikováno v:
Proceedings of The 20th Pacific Basin Nuclear Conference ISBN: 9789811023132
Under fault conditions, it is important maintain the safety of nuclear power plant. Meanwhile, it is also necessary to generate its maximum power output, especially for small modular reactors, to improve the economy. The helical-coiled once-through s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b3d4be0c81212ad28823b790fe8cf4d
https://doi.org/10.1007/978-981-10-2314-9_75
https://doi.org/10.1007/978-981-10-2314-9_75
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :1567
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::26755d8a3c805f343498334fd055b8cf
https://doi.org/10.1299/jsmeicone.2019.27.1567
https://doi.org/10.1299/jsmeicone.2019.27.1567