A risk-based evaluation of the impact of key uncertainties on the prediction of severe accident source terms—STU
| Autor: | H-G Friederichs, M. Sonnenkalb, L. Spanier, H. Wennerstrom, L.M.C. Dutton, M. Gren, E. Grindon, T. Routamo, S. Outa, Jorma Jokiniemi, C.S. Santamaria, M-H Boschiero, P. Garcia-Sedano, M. Auglaire, B. Centner, J-L Droulas, M.L. Ang, V. Gustavsson |
|---|---|
| Rok vydání: | 2001 |
| Předmět: |
Nuclear and High Energy Physics
Fission products Engineering business.industry Mechanical Engineering Pressurized water reactor Context (language use) Nuclear reactor law.invention Nuclear Energy and Engineering Risk analysis (engineering) law Risk analysis (business) Nuclear power plant Forensic engineering media_common.cataloged_instance General Materials Science Light-water reactor European union Safety Risk Reliability and Quality business Waste Management and Disposal media_common |
| Zdroj: | Nuclear Engineering and Design. 209:183-192 |
| ISSN: | 0029-5493 |
| Popis: | The purpose of this project is to address the key uncertainties associated with a number of fission product release and transport phenomena in a wider context and to assess their relevance to key severe accident sequences. This project is a wide-based analysis involving eight reactor designs that are representative of the reactors currently operating in the European Union (EU). In total, 20 accident sequences covering a wide range of conditions have been chosen to provide the basis for sensitivity studies. The appraisal is achieved through a systematic risk-based framework developed within this project. Specifically, this is a quantitative interpretation of the sensitivity calculations on the basis of ‘significance indicators’, applied above defined threshold values. These threshold values represent a good surrogate for ‘large release’, which is defined in a number of EU countries. In addition, the results are placed in the context of in-containment source term limits, for advanced light water reactor designs, as defined by international guidelines. Overall, despite the phenomenological uncertainties, the predicted source terms (both into the containment, and subsequently, into the environment) do not display a high degree of sensitivity to the individual fission product issues addressed in this project. This is due, mainly, to the substantial capacity for the attenuation of airborne fission products by the designed safety provisions and the natural fission product retention mechanisms within the containment. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full Text from ScienceDirect