Conveners
6.8 Experimental Facilities
- Vladimir Semenov
- Basant Kumar Nashine (Indira Gandhi Centre for Atomic Research, Kalpakkam)
Dr
Gunter Gerbeth
(Helmholtz-Zentrum Dresden - Rossendorf)
29/06/2017, 08:00
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
For the safe operation of SFRs there is a growing need for small and medium sized liquid metal experiments to study various thermohydraulic and safety aspects, comprising effects such as flow metering, local velocity measurements, gas bubble entrainment, and early gas bubble detection. We give a short description of the new large-scale infrastructure DRESDYN (DREsden Sodium facility for DYNamo...
Dr
Mariano Tarantino
(ENEA)
29/06/2017, 08:20
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The CIRCE-ICE experimental facility, designed and hosted at ENEA Brasimone R.C., is a large pool multi-purpose integral test facility devoted to support the Thermal-Hydraulic design of Gen IV Liquid Metal Fast Reactor.
Thermal stratification phenomena in HLM pool may induce significant thermal loads on the structure in addiction to existing mechanical loads. Moreover, vertical temperature...
Mr
Frédéric SERRE
(Commissariat à L'Energie Atomique et aux Energies Alternatives(CEA))
29/06/2017, 08:40
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demonstration) is a technological demonstrator of sodium-cooled fast reactor (SFR) designed by the CEA with its industrial partners, with very high levels of requirements. Innovative options have been integrated to enhance the safety, to reduce the capital cost and improve the efficiency, reliability and operability,...
Mr
P. Selvaraj
(Indira Gandhi Centre For Atomic Research)
29/06/2017, 09:00
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Fast reactor components are required to work in hostile atmosphere of sodium, high temperature and radiation. Sodium testing of components before installation in reactor is essential for design validation and safe operation of the reactor. Components like Transfer arm, Inclined fuel transfer machine, Control and Safety Rod Drive Mechanism (CSRDM) and Diverse Safety Rod Drive mechanism (DSRDM),...
Mr
Vladislav Sizarev
(JSC N.A. Dollezhal Research and Development Institute of Power Engineering)
29/06/2017, 09:20
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
This report deals with a computational and experimental justification for the search of the optimal spacing for the axial fuel assembly (FA) spacer grid (SG) arrangement in reactor facilities subject to vibration resistance requirements. Practically, as is known, the spacing selection is postulated at the present time based on the earlier selected FA dimensions for both effective and...
Prof.
Tao Zhou
(Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)
29/06/2017, 09:40
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Liquid lead-alloy is a potential candidate coolant for fast reactor and Accelerator Driven System (ADS) subcritical system because of its many unique nuclear, thermophysical and chemical attributes. Chinese Academy of Sciences (CAS) had launched a project to develop ADS and lead-based fast reactors technology since 2011. China LEAd-based Reactor (CLEAR) was selected as the reference reactor....
