Transfer learning network for nuclear power plant fault diagnosis with unlabeled data under varying operating conditions

J Li, M Lin, Y Li, X Wang - Energy, 2022 - Elsevier
The performance of data-driven nuclear power plant fault diagnosis models trained by
limited data cannot be guaranteed, the distribution discrepancy between training set (source …

Generalization analysis and improvement of CNN-based nuclear power plant fault diagnosis model under varying power levels

M Lin, J Li, Y Li, X Wang, C **, J Chen - Energy, 2023 - Elsevier
The domain discrepancy caused by power level gap between training set (source domain)
and test set (target domain) limits the generalization of data-driven models in practical …

Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3. 2 code

A Hedayat, H Davilu, J Jafari - Progress in Nuclear Energy, 2007 - Elsevier
In this paper, a loss of coolant accident (LOCA) in Tehran research reactor (TRR) is
analyzed. The following procedure consists of three major parts. First, a RELAP5 …

[HTML][HTML] Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete …

A Hedayat - Nuclear Engineering and Technology, 2017 - Elsevier
In this paper, a complete station blackout (SBO) or complete loss of electrical power supplies
is simulated and analyzed in a downward cooling 5-MW pool-type Material Testing Reactor …

Main control system verification and validation of NPP digital I&C system based on engineering simulator

M Lin, D Hou, P Liu, Z Yang, Y Yang - Nuclear Engineering and Design, 2010 - Elsevier
Full-scope digital instrumentation and controls system (I&C) technique is being introduced in
Chinese new constructed Nuclear Power Plant (NPP), which mainly includes three parts …

Development and application of an extensible engineering simulator for NPP DCS closed-loop test

D Hou, M Lin, Z Xu, Y Yang - Annals of Nuclear Energy, 2011 - Elsevier
LinAo Nuclear Power Plant (NPP) Phase II is a newly-built CPR1000 reactor in China, and
many new technologies including the incorporation of digital control system (DCS) …

Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3. 2 code

A Hedayat - Kerntechnik, 2019 - degruyter.com
In this paper, a 5 MW open pool type research reactor is simulated and analyzed to check
and pass a complete and practical safety assessment against various LOFA scenarios …

Coupling methods for parallel running RELAPSim codes in nuclear power plant simulation

Y Li, M Lin, Y Yang - Nuclear Engineering and Design, 2016 - Elsevier
When the plant is modeled detailedly for high precision, it is hard to achieve real-time
calculation for one single RELAP5 in a large-scale simulation. To improve the speed and …

System simulation of nuclear power plant by coupling Relap5 and Matlab/Simulink

M Lin, D Hou, Z Xu, Y Yang… - International …, 2006 - asmedigitalcollection.asme.org
Since RELAP5 code has general and advanced features in thermal-hydraulic computation, it
has been widely used in transient and accident safety analysis, experiment planning …

Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system—I: Scheme of OLVT

Y Li, M Lin, Z Yang, Y Hou, Y Yang - Annals of Nuclear Energy, 2017 - Elsevier
With a shift in technology to digital systems as the result of analog obsolescence and digital
functional advantages, existing plants have begun to replace some current analog …