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

Session

6.2 Thermal Hydraulics Calculations and Experiments

26 Jun 2017, 15:10

Yekaterinburg

Conveners

6.2 Thermal Hydraulics Calculations and Experiments

• Selvaraj Perumal (Indira Gandhi Centre For Atomic Research, Department of Atomic Energy, Kalpakkam, India)
• Nastasia Mosunova (Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))

249. Thermal Hydraulic Study of Steam Generator of PGSFR

Dr Jonggan Hong (KAERI)

26/06/2017, 15:10

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

In Prototype Gen-IV Sodium cooled Fast Reactor (PGSFR), integral once-through type, counter-flow shell-and-tube heat exchanger with straight vertical tubes was adopted for steam generators. Reliable operation of the steam generators has been a key issue through operating experience of foreign sodium cooled fast reactors because it is one of the most important components deciding the plant...

310. EFFECT OF INLET TEMPERATURE AND OPERATING LINEAR HEAT RATING (LHR) ON THE MAXIMUM ACHIEVABLE BURNUP OF MK-1 CARBIDE FUEL IN FBTR

Mr CLEMENT RAVI CHANDAR SOWRINATHAN (IGCAR, INDIA)

26/06/2017, 15:30

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

India had constructed and is operating Fast Breeder Test Reactor (FBTR) with Mixed Carbide Fuel, a first of its kind in the world, as driver fuel. Mixed Carbide was chosen as fuel due to its high stability with Pu rich fuel, compatibility with coolant and for its better thermal performance. Being a unique fuel of its kind without any irradiation data, it was decided to use the reactor itself...

232. Extension to Heavy Liquid Metal coolants of the validation database of the ANTEO+ sub-channel code

Mr Francesco Lodi (University of Bologna)

26/06/2017, 15:50

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

Among the numerous numerical methods available for preliminary design verification purposes, the sub-channel one has historically been the reference, thanks to its ability to cover the scale between CFD and system codes which is the one of particular interest for the core designer. Recently, the sub-channel code for liquid metal applications ANTEO+ has been developed by ENEA and a...

440. Density of sodium along the Liquid-Vapor Coexistence Curve, including the Critical Point

Dr M. Laura Japas (CNEA - Argentina)

26/06/2017, 16:10

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

Sodium densities along the whole liquid-vapor coexistence curve are reanalyzed using the equation proposed by Apfelbaum and Vorob’ev(1). The formulation has built-in the correct behavior for liquid and vapor densities, both at low temperature and in the near-critical region. Thus, it satisfactorily represents the available experimental data in the low and intermediate temperature range, while...

439. Experimental investigations of velocity and temperature fields, stratification phenomena in a integral water model of fast reactor in the steady state forced circulation

Mr Aleksandr Trufanov (SSC RF-IPPE)

26/06/2017, 16:30

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

The results of experimental investigations of local velocities for height and radius of the top of the camera in the plane in the direction from the core center to the intermediate heat exchanger and the temperature of the coolant in the upper (hot) chamber, and other elements of the circulation circuit on the integrated water model of the reactor on fast neutrons (scale ~ 1:10) for the...

455. Development and Validation of Multi-scale Thermal-Hydraulics Calculation Schemes for SFR Applications at CEA

Mr Yannick Gorsse (CEA-Saclay)

26/06/2017, 16:50

Track 6. Test Reactors, Experiments and Modeling and Simulations

ORAL

In the framework of the ASTRID Gen4 SFR project, extensive R&D efforts are under way to improve and better validate the SFR thermal-hydraulics codes available at CEA. These efforts include : - The development and validation of SFR-specific models in CATHARE. Developed at CEA, CATHARE is the reference STH code for French LWR safety studies : SFR developments are being integrated and...