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凌元锦  教授/硕士生导师

邮箱:qustling@163.com

凌元、日本归侨、博士、教授、士生导师。在日本工作期,担任Techno Management Solutions Ltd.公司董事、开、首席研究。回国后,立了科大件技有限公司,并出任董事。公司是集学研于一体的高新技,依托大学的技和人力优势,开件著作的化工安全生命周期管理系集成PSLMStation该软件是国上少有的穿化工安全生命周期管理全程,包括在研设计、建造、生运行、维护各不同段上的安全管理一体化系集成件。件集成了算机HAZOP分析、故障生成与分析、可设备管理、在线故障断、可更管理、操作程可化管理六大系,在日本多家石化企和科研位得到了验证。技成果在20123得了日本化学工程学会技术奖,并在日本申利。

研究方向

化工安全智能技、化工安全生命周期管理系集成、算机助危分析与价、基于风险评估的设备检测和管理技RBI&RBM)、化工设备概率安全价(PSA)。

科研成果

1. 化工安全件:化工安全生命周期管理系集成平台PSLMStation算机HAZOP分析HAZOPStation、故障生成与分析FTAStation、可设备管理PMVStation、在线故障断系OFDStation、可更管理MOCVStation、操作程可化管理SOPMStation

2. 获奖20123得日本化学工程学会技术奖获奖项目名称:化工设备管理/操作运行整合模型开用。

3. 利:化工风险评估智能化装置,日本国家,特2010- 244439

代表性

术杂

Teiji KitajimaTetsuo FuchinoYukiyasu ShimadaLing YuanjinUse Case Driven Development of a Risk Management Tool with Business Process Model for Chemical PlantsComputer Aided Chemical Engineering30912-9162012

Yuan-Jin Ling Koichi MAKINoritaka YUSAKenzo MIYA Development of the Optimization Model for TBM Time Intervals in Maintenance Methods Combined TBM and CBMTransactions of the Atomic Energy Society of JapanVol.6No.32007Japan

Kentaro TAKASE Yuan-Jin LingTakahiko HIDAStudy on Probabilistic design of Nuclear reactorLRFD Method and Application to Nuclear Reactor Piping designJapan Society of MaintenologyVol.4No.42006Japan

Yuan-Jin Ling Kazuhiko Suzuki Takehisa Kohda A Mathematical Model of Independent Protection LayerTransactions of the Society of Instrument and Control EngineersVol.42No.12006Japan

Yuan-Jin Ling Kazuhiko Suzuki Takehisa Kohda A Mathematical Model of Protective System with Self-DiagnosisTransactions of the Society of Instrument and Control EngineersVol.41No.32005Japan

Yuan-Jin Ling Kazuhiko Suzuki Takehisa Kohda Optimal Risk-Based Inspection Policy for Safety Instrumentation SystemTransactions of the Society of Instrument and Control EngineersVol.40No.32004Japan

Yuan -Jin Ling Takehisa KohdaKazuhiko SuzukiYukiyasu Shimada Reliability and Safety of Safety Monitoring System Considering Intermittent and Complete FailureTransactions of the Society of Instrument and Control EngineersVol.39No.22003Japan

议论

Yukiyasu ShimadaTeiji KitajimaYuanjin Ling Integrated risk management system based on IPL concept for chemical processesUSB Proceedings of 11th International Probabilistic Safety Assessment and Management Conference & The Annual European Safety and Reliability Conference 2012PSAM11 & ESREL201220-Tu5-2.

Yuan-Jin Ling Yukiyasu ShimadaTeiji Kitajima Fault Tree Synthesis Based on HAZOP LogProceedings of the 76th SCEJ Annual  MeetingTokyoJapan( 2011)

Teiji Kitajima Yukiyasu Shimada Yuan-Jin Ling An Engineering Support Platform Based on Process Safety AssessmentProceedings of the 75th SCEJ Annual  MeetingKagoshimaJapan( 2010)

Teiji KitajimaTetsuo FuchinoYukiyasu ShimadaYuji NakaYuan-Jin LingKensuke IuchiKoji Kawamura A New Scheme for Management of Change Support Based on Hazop Log20th European Symposium on Computer Aided Process EngineeringComputer Aided Process EngineeringElsevierVolume 28pp. 163-168Jun. 2010.

Yuan-Jin LingNoritaka YUSAKoichi MAKIKenzo MIYATakahiko HIDA Development of Risk-Informed Piping Optimal Design MethodProceedings of the JSME Dynamics and Design Conference 2007225HiroshimaJapan2007

Yuan-Jin LingNoritaka YUSAKoichi MAKIAkihiro TAGAWA Evaluating Availability of Pipe Wall Thinning Monitoring by Monte Carlo Simulation MethodProceedings of the 4th JSM Annual ConferenceP27FukuiJapan2007

Yuan-Jin LingNoritaka YUSAKoichi MAKIKenzo MIYATakashi SHIMIZU Study on Best-Mix of CBM and TBM by Monte Carlo Simulation MethodProceedings of the AESJ Fall MeetingC14Kita-kyushuJapan2007

Yuan-Jin LingKentaro TAKASEKoichi MAKI Study on Best-Mix of CBM and TBM Considering Effect of Spurious Diagnostics Using State Transition ModelProceedings of the 3rd JSM Annual ConferenceP19SendaiJapan2006

Yuan-Jin LingKentaro TAKASEKoichi MAKITakahiko HIDA Study on Prediction of Thickness in Nuclear Reactor Piping and Estimation of Inspection Intervals by Applying Reliability-base MethodProceedings of the 3rd JSM Annual ConferenceP18SendaiJapan2006

Yuan-Jin LingKentaro TAKASEKoichi MAKITakahiko HIDA Development of Calculation Code of LRFD method and Application to Nuclear Reactor PipingProceedings of the AESJ Fall MeetingL16SapporoJapan2006

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