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Regional Workshop on Advances in the Modelling and Simulation of Thermal Hydraulics in Liquid Metal Cooled Fast Reactors

6 – 10 Apr 2020
New Delhi, India
Event code: EVT1904440
Postponed

The nuclear industry has from its inception recognized the important role of fast reactors and related fuel cycles in ensuring the long-term sustainability of nuclear power. Many of the International Atomic Energy Agency’s (IAEA’s) Member States are actively developing reactor, coolant, fuel and fuel cycle technologies related to fast reactors. In addition to current fast reactor construction projects, several countries are engaged in intense research and development programmes for the development of innovative, or Generation IV, fast reactor concepts. Reactor technologies under development include sodium, lead, gas, molten salt and even supercritical water cooled systems and technologies and accelerator-driven systems. In parallel, several demonstration projects, ranging from small to large scale, are under study or construction.

Liquid metal cooled fast reactors (LMFRs) are one of the main technologies being pursued for development and deployment. The most mature fast reactor technology, the sodium cooled fast reactor, has more than 400 reactor-years of experience acquired through the design, construction, operation and decommissioning of experimental, prototype, demonstration and commercial units operating in a number of countries. Lead and lead-bismuth cooled fast reactors are also under development at the national and international levels.

The modelling and simulation of thermal hydraulics play a crucial role not only in understanding the physical phenomena of reactors, but also for their safe operation. This workshop aims to provide information on and explain recent developments in the modelling and simulation of thermal hydraulics in LMFRs.

Objectives:

The objective of the event is to review designs of liquid metal cooled fast reactors and the related scientific and technological aspects, in particular advanced physical and mathematical models for numerical simulation of reactor thermal hydraulics. It will also offer a forum for active discussions and for sharing new ideas among the participants and lecturers.

Topics

It is envisaged that the following topics will be addressed and discussed during the workshop:

  • Thermal hydraulics of advanced LMFRs;
  • Overview of design and operation of fast reactors worldwide;
  • Development of fast reactor technology in India;
  • Thermal hydraulic feedback experience from FBTR operation;
  • Commissioning experience with respect to thermal hydraulics of PFBR;
  • Regulators’ view on fast reactor thermal hydraulics with respect to safety;
  • Consideration of pool hydraulic aspects in fast reactor design;
  • Challenges in natural convection-based decay heat removal;
  • Hydraulic experiments in support of LMFR technology;
  • Engineering qualification through sodium experiments: scaling and instrumentation challenges;
  • Coolant–structure interaction issues in fast reactor systems;
  • Experimental investigations of thermal hydraulics related to core disruptive accidents (CDAs);
  • Experimental studies of LMFR thermal hydraulic and empirical correlations for friction factors and heat transfer coefficients;
  • Subchannel analysis of LMFR fuel assemblies;
  • System thermal hydraulics of LMFRs;
  • CFD modelling of LMFRs;
  • Advanced investigations in the area of gas entrainment;
  • Experimental and theoretical investigation of magnetohydrodynamics of electromagnetic pumps;
  • Sodium boiling: experimental studies and modelling approach;
  • Containment thermal hydraulics with respect to post-CDA phenomenon;
  • Fuel–coolant interaction; and
  • Debris bed cooling and core catcher performance during post-accident heat removal.

Please read the information sheet for more detailed information regarding participation in the workshop.

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