International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)

Session

6.6 Coupled Calculations

28 Jun 2017, 13:30

Yekaterinburg

Conveners

6.6 Coupled Calculations

• Valery Strizhov (Nuclear Safety Institute)
• Zhi-gang Zhang (Harbin Engineering University)

561. Codes of New Generation Developed for Breakthrough Project

Prof. Valery Strizhov (Nuclear Safety Institute)

28/06/2017, 13:30

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

In frame of Breakthrough project the system of codes of a new generation is being developing for justification of operational characteristics and safety of the NPP with sodium, lead and lead-bismuth coolants utilizing closed fuel cycle. Use of the code system by design and industry organizations ensure reduction of uncertainties by the use of precise multi-scale models and more detailed...

576. Research and Development on Simulator of Fast Reactor in China

Prof. ZhiGang ZHANG (Harbin Engineering University), Prof. ZhiJian Zhang (Harbin Engineering University)

28/06/2017, 13:50

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

With the closed fuel cycle strategy, China develops the fast reactor and advanced reprocessing technology, which supports the sustainable development of China nuclear energy. Technical solutions for the simulator of China Experimental Fast Reactor (CEFR), modeling and simulation are mainly introduced. CEFR adopted a pool-type FR technology with three-loops, which has 216 subsystems. The full...

299. Neutronics Experimental Verification for ADS with China Lead-based Zero Power Reactor

Prof. qingsheng wu (Institute of Nuclear Energy Safety Technology, CAS · FDS Team)

28/06/2017, 14:10

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

Abstract: An Accelerator Driven System (ADS) project for nuclear waste transmutation has been launched by Chinese Academy of Sciences (CAS) since 2011. China LEAd-based Reactor (CLEAR) was selected as the reference reactor for the CAS ADS project and was designed and developed by Institute of Nuclear Energy Safety Technology (INEST), CAS. According to the research and development roadmap of...

184. Coupled calculations for the fast reactors safety justification with the EUCLID/V1 integrated computer code

Mrs Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))

28/06/2017, 14:30

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

The EUCLID/V1 integrated computer code is designed for the safety analysis and justification of the new generation NPPs with liquid metal cooled fast reactors under normal operating conditions, design basis accidents and beyond design basis accidents. The EUCLID/V1 code includes the system thermohydraulics module, spatial time-dependent neutronics module, quasi two-dimensional fuel rod module...

59. Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code

Eirik Eide Pettersen (Paul Scherrer Institut)

28/06/2017, 14:50

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

Fast reactors that circulate liquid fuel exhibit a strong coupling between neutronics and thermal-hydraulics that necessitates the use of coupled multi-physics codes to study dynamic behaviour. Presently, most such tools employ computational fluid dynamics (CFD) to resolve thermal-hydraulics. This paper concerns an alternative approach in which the system code TRACE is used to compute...