The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
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C.-N. Wang
Abstract
The Fukushima nuclear disaster in 2011 has raised widespread concern over the safety of nuclear power plants. This study employed knowledge management in conjunction with the Teoriya Resheniya Izobreatatelskih Zadatch (TRIZ) method in the formulation of a database to facilitate the evaluation of post-fire safe shutdown capability with the aim of safeguarding nuclear facilities in the event of fire. The proposed approach is meant to bring facilities in line with US Nuclear Regulatory Commission (NRC) standards. When implemented in a case study of an Asian nuclear power plant, our method proved highly effective in the detection of 22 cables that fell short of regulatory requirements, thereby reducing 850,000 paths to 0. This study could serve as reference for industry and academia in the development of systematic approaches to the upgrading of nuclear power plants.
Kurzfassung
Die Nuklearkatastrophe von Fukushima 2011 führte zu weitverbreiteten Bedenken in Bezug auf die Sicherheit von Kernkraftwerken. In dieser Studie wurde Wissensmanagement in Verbindung mit der Teoriya Resheniya Izobreatatelskih Zadatch (TRIZ) Methode bei der Formulierung eines Datenbestands zur Erleichterung der Bewertung des sicheren Abschaltens nach einem Brand angewendet mit dem Ziel der Sicherung von Kernkraftwerken im Brandfall. Der vorgeschlagene Ansatz soll kerntechnische Anlagen auf einen Stand mit den Standards der US Nuclear Regulatory Commission (NRC) bringen. Wendet man diese Methode im Rahmen einer Fallstudie bei einem asiatischen Kernkraftwerk an, zeigt sich die Methode sehr effektiv beim Nachweis von 22 Leitungen die den gesetzlichen Anforderungen nicht genügen. Diese Studie könnte als Referenzmethode für Industrie und Academia dienen bei der Entwicklung eines systematischen Ansatzes zur Verbesserung der Sicherheit von Kernkraftwerken.
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© 2017, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Modelling Human Resource Requirements for the Nuclear Industry in Europe
- Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
- The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
- Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
- Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
- The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
- Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
- Anti-neutrino flux in a research reactor for non-proliferation application
- Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
- Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
- Internal and external hazards inside the containment in case of an emergency situation
- Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Modelling Human Resource Requirements for the Nuclear Industry in Europe
- Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
- The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
- Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
- Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
- The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
- Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
- Anti-neutrino flux in a research reactor for non-proliferation application
- Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
- Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
- Internal and external hazards inside the containment in case of an emergency situation
- Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
