Zobrazeno 1 - 10
of 94
pro vyhledávání: '"Puzhen GAO"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2023 (2023)
A deep-learning model was proposed for predicting the remaining time to automatic scram during abnormal conditions of nuclear power plants (NPPs) based on long short-term memory (LSTM) and dropout. The proposed model was trained by simulated conditio
Externí odkaz:
https://doaj.org/article/93e3cbf828c44387b18136e93f824fd8
Autor:
Yongchao, Liu, Tong, Li, Kai, Xiao, Jie, Chen, Xin, Tan, Jiahao, Cheng, Sichao, Tan, Bo, Wang, Zhengxi, He, Jihong, Shen, Puzhen, Gao, Ruifeng, Tian
Publikováno v:
In Nuclear Engineering and Design July 2024 423
Autor:
Ashhar Bilal, Puzhen Gao
Publikováno v:
Nuclear Engineering and Design. 408:112321
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fd971dff9ed27938a7c881a2d90cc5a9
https://doi.org/10.1016/j.nucengdes.2023.112321
https://doi.org/10.1016/j.nucengdes.2023.112321
Publikováno v:
Volume 5: Nuclear Safety, Security, and Cyber Security.
In the nuclear reactor, flowing state of surrounding fluid will change structural vibration characteristics of fuel rods, which may lead to severe resonance and damage of fuel rods. Therefore, it is necessary to study structural vibration characteris
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::03dcb1e1cc5d00b60adfb7d50a7c234b
https://doi.org/10.1115/icone29-91975
https://doi.org/10.1115/icone29-91975
Autor:
Ashhar Bilal, Puzhen Gao
Publikováno v:
Volume 8: Computational Fluid Dynamics (CFD) and Applications.
High Cycle Thermal Fatigue is a major degradation mechanism associated with the nuclear power plant piping where hot and cold streams of fluids mix together with a phenomenon called turbulent thermal mixing. It induces significant thermal fluctuation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::07bdd7fda7750c7d28613d976449a7a1
https://doi.org/10.1115/icone29-92926
https://doi.org/10.1115/icone29-92926
Publikováno v:
Volume 7B: Thermal-Hydraulics and Safety Analysis.
Nuclear power in a water-cooled reactor changes with reactivity under the influence of temperature and void fraction. Effects of power oscillations on natural circulation are experimentally investigated with a neutronic-thermo-hydraulic loop to bette
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e1c42387a4af4fb91ff0e64915fe4f35
https://doi.org/10.1115/icone29-93303
https://doi.org/10.1115/icone29-93303
Publikováno v:
Volume 7B: Thermal-Hydraulics and Safety Analysis.
In this study, we experimentally studied the dynamic response of the sinusoidal single-phase flow in a horizontal narrow rectangular pipe. The experimental results show that, in narrow rectangular channel, the flowrate and the pressure drop also meet
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a452a9326be2997f65ff35a7a2852fc0
https://doi.org/10.1115/icone29-92598
https://doi.org/10.1115/icone29-92598
Publikováno v:
Nuclear Engineering and Design. 405:112223
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ebe15f55968b87aac68776579024d53f
https://doi.org/10.1016/j.nucengdes.2023.112223
https://doi.org/10.1016/j.nucengdes.2023.112223
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1b2271975a4a613614d78563739e8f58
https://doi.org/10.2139/ssrn.4030381
https://doi.org/10.2139/ssrn.4030381
Publikováno v:
THE 4TH INTERNATIONAL CONFERENCE ON NUCLEAR ENERGY TECHNOLOGIES AND SCIENCES (ICoNETS) 2021.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f5578ed547305e2bb7d264c5479ed52d
https://doi.org/10.1063/5.0095239
https://doi.org/10.1063/5.0095239