Results 91 to 100 of about 362 (143)

A hybrid BiLSTM-XGBoost model for short-term forecasting of key parameters in nuclear power systems. [PDF]

Sci Rep
Lei J, Peng Z, Ni Z, Ren C, Hu H, Gao X, Xu K, Cao Y.   +7 more
europepmc   +1 more source

Entropy-Driven Intelligent Diagnosis for SMR Loss of Coolant Accidents: A CNN-LSTM-Attention Hybrid Model for Break Size Assessment. [PDF]

Entropy (Basel)
Yang L, Lei J.
europepmc   +1 more source

Identification and diagnosis of flow instability in parallel channel systems using machine learning. [PDF]

Commun Eng
Peng C, Wang X, Tian R, Wu J, Deng J.
europepmc   +1 more source

Adaptive Forecasting of Nuclear Power Plant Operational Status Under Sensor Concept Drift Using a Bridging Distribution Adaptive Network. [PDF]

Sensors (Basel)
Xu K, Liu L, Lan Y, He S, Fang H, Cheng M.   +5 more
europepmc   +1 more source

Preliminary risk assessment of in-vessel leakage accident in ITER. [PDF]

Sci Rep
Duan Q, Fang X, Chen S, Xie H, Wang C, Wang D.   +5 more
europepmc   +1 more source

An integrated method for the leakage fault mode diagnosis and life prediction of the reactor coolant pump. [PDF]

PLoS One
Shao Y, Kang R, Fu J, Liu J.
europepmc   +1 more source

Flow stability and distribution in horizontal serpentine tube bundles with vertical headers. [PDF]

Heliyon
Illyés V, Thanheiser S, Ettlinger F, Schulz M, Haider M.   +4 more
europepmc   +1 more source

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BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D

Progress in Nuclear Energy, 2021
Abstract Passive safety systems are currently implemented or under consideration in several advanced nuclear plants. In the Best-Estimate Plus Uncertainty (BEPU) approach it is fundamental to qualify Best-Estimate thermal-hydraulic system codes and models for the phenomena typical of passive systems and to quantify the uncertainty of calculations. In
Fulvio Mascari, Cristina BERTANI, Andrea Bersano   +2 more
exaly   +2 more sources

COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes

Nuclear Technology, 1992
The best-estimate thermal-hydraulic codes RE-LAP5/MOD3 and COBRA-TF were adopted to the Apollo DN 10000 workstation and subsequently merged.
Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim, Soon Heung Chang   +3 more
openaire   +1 more source

Investigations on RELAP5-3D to RELAP5-3D Coupling Methodology by PVMEXEC

Volume 3: Thermal-Hydraulics, 2016
In the framework of a BEPU (Best Estimate Plus Uncertainty) approach within the licensing process of a nuclear power plant, the need to extend the resources of nuclear system thermal-hydraulics codes, such as RELAP5-3D, arises to allow more detailed simulations of the complex 3D reality of Nuclear Power Plants (NPPs), either under normal steady-state ...
Valeria Parrinello, Marco Lanfredini, Alessandro Petruzzi, Marco Cherubini   +3 more
openaire   +1 more source