Search Results - "Liang, Qingzhu"

Probabilistic risk assessment model for released tritium into the environment for CFETR by Liang, Qingzhu, Xu, Xinyan, Peng, Changhong

“…The China Fusion Engineering Test Reactor (CFETR) is the next facility in the Chinese roadmap to realize sustainable-clean fusion energy. Because of the large…”
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Reliability Assessment for a Safety-Related Digital Reactor Protection System Using Event-Tree/Fault-Tree (ET/FT) Method by Xiao, Jun, Guo, Yun, Xiao, Peng, Liu, Mingxing, Liang, Qingzhu, Peng, Changhong

“…The aim of this study is to verify if the reliability of a digital four-channel RPS under the design phase satisfies the specified target and to identify the…”
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A reliability model for systems subject to mutually dependent degradation processes and random shocks under dynamic environments by Liang, Qingzhu, Yang, Yinghao, Peng, Changhong

“…•A reliability for systems subject to mutually dependent degradation processes are proposed.•The effect of random shocks and dynamic environments are…”
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A multi-state Semi-Markov model for nuclear power plants piping systems subject to fatigue damage and random shocks under dynamic environments by Liang, Qingzhu, Peng, Changhong, Li, Xiangyu

“…•A multi-state Semi-Markov model for degraded piping systems in nuclear power plants was proposed.•The effects of the stochastic environment and random shocks…”
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Reliability analysis of multi-component systems subjected to dependent degradation processes and random shocks in dynamic environments by Liang, Qingzhu, Liu, Songlin, Peng, Changhong

“…This article presents reliability models for multi-component systems subjected to multiple internally dependent degradation processes and external shocks in…”
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Analysis of simplification in Markov state-based models for reliability assessment of complex safety systems by Liang, Qingzhu, Yang, Yinghao, Zhang, Hang, Peng, Changhong, Lu, Jianchao

“…•A method for simplification in Markov state-based models for reliability assessment of complex safety systems based on system decomposition and using…”
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A cumulative damage model for tubes in nuclear power plants subject to continuous degradation and multi-effect shocks under dynamic environments by Xie, Xiwen, Peng, Changhong, Liang, Qingzhu

“…•A cumulative damage model for piping system subject to both continuous degradation and random shocks is investigated.•Degradation and random shocks related to…”
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Failure probability evaluation for a weld of the heat pipe in the Mega-Power heat pipe cooled reactor by Xu, Xinyan, Liang, Qingzhu, Peng, Changhong

“…•A probabilistic fracture mechanics analysis code considering the unique characteristics of heat pipe is developed.•Failure probability evaluation for a…”
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Probabilistic fracture mechanics analysis of heat transfer tube in floating nuclear power plant under multiple failure mechanisms by Xu, Xinyan, Xie, Xiwen, Liang, Qingzhu, Peng, Changhong

“…•A probabilistic fracture mechanics integrating Bayesian method failure analysis code is developed.•Failure probability of heat transfer tube in floating…”
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Break probability evaluation for a weld in piping of the water-cooled ceramic breeder blanket for CFETR by Liang, Qingzhu, Guo, Yun, Peng, Changhong, Wang, Dianle, Lu, Jianchao

“…•A probabilistic model for piping breakage evaluation is developed for the water-cooled breeder blanket for CFETR.•Break probabilities of a weld in piping of…”
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