Challenges on innovations of newly-developed safety analysis codes
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Y. Yang
Abstract
With the development of safety analysis method, the safety analysis codes meet more challenges. Three challenges are presented in this paper, which are mathematic model, code design and user interface. Combined with the self-reliance safety analysis code named COSINE, the ways of meeting these requirements are suggested, that is to develop multi-phases, multi-fields and multi-dimension models, to adopt object-oriented code design ideal and to improve the way of modeling, calculation control and data post-processing in the user interface.
Kurzfassung
Mit der Weiterentwicklung der Methoden der Sicherheitsanalysen wachsen auch die Anforderungen an die Programme, mit denen diese Analysen durchgeführt werden. Innovationsmöglichkeiten bestehen bei den mathematischen Modellen, dem Codedesign und den Nutzeroberflächen. Am Beispiel des eigenständigen Programms COSINE werden Wege aufgezeigt, die zu multi-phasen, multi-Feld und multi-dimensionalen Modellen führen, die das objektorientierte Codedesign ideal umsetzen und den Nutzer beim Modellieren, Rechnen und Postprozessing verbessert unterstützen.
References
1 Yang, Y.; Chen, Y.; Zhang, H.: Core and system analysis integrated code platform developed in China. American Nuclear Society Annual Meeting, No. 4195, June 26–30, 2011, Hollywood, FLSearch in Google Scholar
2 Yang, Y.; Chen, Y.; Zhang, H.; Yu, H.; Zhao, G.; FuX.; Liu, Z.; Mo, W.: Requirement analysis and primary design of COSINE code. American Nuclear Society Annual Meeting, No. 5805, June 24–28, 2012, Hyatt Regency Chicago, Chicago, ILSearch in Google Scholar
3 The RELAP5 Code Development Team: RELAP5/MOD3 code manual volume I: code structure, system models, and solution methods. Idaho National Engineering Laboratory report, INEL-95/0174, June 1995Search in Google Scholar
© 2016, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Selected contributions from 1th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
- Technical Contributions/Fachbeiträge
- Scientific codes developed and used at GRS – Nuclear simulation chain
- Challenges on innovations of newly-developed safety analysis codes
- Validation of system codes for plant application on selected experiments
- Progress of Experimental Research on Nuclear Safety in NPIC
- Severe accident research activities at Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
- THAI experimental programme for containment safety assessment under severe accident conditions
- A spray cooling technique for spent fuel assembly stored in pool
- KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors
- Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors
- 10.3139/124.110680
- Validation of the ATHLET-SC code by trans-critical transient data
- Qualification of CFD-models for multiphase flows
- The reactor dynamics code DYN3D
- Critical flow phenomena and modeling in advanced nuclear safety technology
- 10.3139/124.110682
- Safety and security aspects in design of digital safety I&C in nuclear power plants
- Thermohydraulic safety issues for liquid metal cooled systems
- Design and safety analysis of the helium cooled solid breeder blanket for CFETR
- Qualification of pebble fuel for HTGRs
- High temperature reactors for cogeneration applications
