Technical Sessions Description

General Thermal Hydraulics

In this General Thermal Hydraulics sessions the following subjects are solicited: Small and large-scale thermal-hydraulic experiments, laboratory and industrial measuring methods for thermal-hydraulic processes, basic single, two-phase and multiphase flow and heat transfer, thermal hydraulics simulations, system and component thermal-hydraulic codes development, separate thermal-hydraulic effects (critical heat flux, flooding, flow pattern transitions, two-phase chocked flow, etc.), sub-channel thermal hydraulics, containment thermal hydraulics and aerosol transport, integral nuclear power plants behaviors under transient and malfunction conditions, thermal-hydraulics of molten core and severe accidents, coupling to system codes (like neutron kinetics, BoP, I&C).

Computational Thermal Hydraulics

This session is intended to provide an opportunity to the engineers and scientist to present recent computational thermal hydraulic development, application, validation and verification, code comparison and benchmarking, and uncertainty determination.   Papers are solicited which deal with any aspect of thermal hydraulic calculation and Computational Fluid Dynamics (CFD) work.

Authors and presenters are invited to participate in this event to expand understanding and promotion of efforts and disciplines in the area of Computational Thermal Hydraulics and Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes. Dissemination of knowledge by presenting results, new developments, and novel concepts in computational techniques, Neutronics methods and coupled Codes, CFD and thermal-hydraulic codes coupling are solicited.

General Two-Phase Flow

This session is intended to provide an opportunity to the engineers and scientist to present recent developments in basic two phase flow and heat transfer.   In this sessions the following subjects are solicited: experiments in basic two phase flow and heat transfer involving gas and liquids, gas and solids in pipe or channels; instrumentation and new methods of measurement of two-phase flow parameters such as interfacial area concentration, void fraction and bubble drift velocity; development of models on key two phase flow phenomena, such as entrainment, flooding, critical flow, flow regime transition, and others.

 

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Sessions:

General Thermal Hydraulics

In this General Thermal Hydraulics sessions the following subjects are solicited: Small and large-scale thermal-hydraulic experiments, laboratory and industrial measuring methods for thermal-hydraulic processes, basic single, two-phase and multiphase flow and heat transfer, thermal hydraulics simulations, system and component thermal-hydraulic codes development, separate thermal-hydraulic effects (critical heat flux, flooding, flow pattern transitions, two-phase chocked flow, etc.), sub-channel thermal hydraulics, containment thermal hydraulics and aerosol transport, integral nuclear power plants behaviors under transient and malfunction conditions, thermal-hydraulics of molten core and severe accidents, coupling to system codes (like neutron kinetics, BoP, I&C).

Computational Thermal Hydraulics

This session is intended to provide an opportunity to the engineers and scientist to present recent computational thermal hydraulic development, application, validation and verification, code comparison and benchmarking, and uncertainty determination.   Papers are solicited which deal with any aspect of thermal hydraulic calculation and Computational Fluid Dynamics (CFD) work.

Authors and presenters are invited to participate in this event to expand understanding and promotion of efforts and disciplines in the area of Computational Thermal Hydraulics and Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes. Dissemination of knowledge by presenting results, new developments, and novel concepts in computational techniques, Neutronics methods and coupled Codes, CFD and thermal-hydraulic codes coupling are solicited.

General Two-Phase Flow

This session is intended to provide an opportunity to the engineers and scientist to present recent developments in basic two phase flow and heat transfer.   In this sessions the following subjects are solicited: experiments in basic two phase flow and heat transfer involving gas and liquids, gas and solids in pipe or channels; instrumentation and new methods of measurement of two-phase flow parameters such as interfacial area concentration, void fraction and bubble drift velocity; development of models on key two phase flow phenomena, such as entrainment, flooding, critical flow, flow regime transition, and others.

Thermal-Hydraulics of Advanced Systems

This session is intended to provide a forum for the presentation of recent work involving Gen IV, Space, and Novel Applications.  Topics anticipated include thermal-hydraulic design, performance, process studies, and limits of these advanced systems.  Nuclear professionals supporting Prismatic or Pebble-Bed Gas Reactors, Gas Fast Reactors, Supercritical Water Reactors, Liquid Metal Reactors, Molten Salt Reactors, etc. as they apply to power generation, process heat systems, hydrogen production, or similar activity are encouraged to submit their work.

Severe Accident Phenomena and Engineered Features

This session is intended to provide a forum for the presentation of recent work to increase our understanding of, and to develop practical measures against, severe accident progression.  Topics may include recent experimental results, investigations to evaluate proposed methods for mitigating consequences, and enhancements to methods for predicting event progression. In particular, authors are encouraged to address topics directly applicable to advanced reactors proposed for design certification or currently under construction.

General Two-Phase Flow

This session is intended to provide an opportunity to the engineers and scientist to present recent developments in basic two phase flow and heat transfer.   In this sessions the following subjects are solicited: experiments in basic two phase flow and heat transfer involving gas and liquids, gas and solids in pipe or channels; instrumentation and new methods of measurement of two-phase flow parameters such as interfacial area concentration, void fraction and bubble drift velocity; development of models on key two phase flow phenomena, such as entrainment, flooding, critical flow, flow regime transition, and others.

Uncertainty Treatment in Nuclear Science and Engineering

This session is a forum for presentations related to uncertainty treatment.  In particular, authors are encouraged to present original/recent work in related topics including but not limited to quantification of uncertainties, statistical treatment, sampling techniques, sensitivity studies, best-estimate techniques, and conforming with current regulations  as they apply to nuclear science and engineering in general and to computational thermal-hydraulics and reactor safety in particular.

Thermal Hydraulics Aspects and Licensing Status of Generation III/III+ Submittals

The session is intended to provide a forum for engineers and scientists to share experiences and lesson learned with regard to resolution of important thermal hydraulic issues for the licensing of generation III/III+ nuclear power plant. Papers are solicited from all parties involved in the design and licensing of the next generation nuclear power plant, which include vendors, utilities and regulators. Focus is the understanding of key thermal-hydraulic phenomena which have been considered in assessing the plant safety margins.  Contributions are expected in the identification of scenarios, analysis of experiments, the development of modeling techniques, the assessment of the models against test data and the determination of their bias and uncertainties.

Thermal Hydraulics of Spent Fuel

This session will be a forum for discussions on thermal-hydraulic phenomena related to spent fuel.  The topics include, but are not limited to, normal and off-normal conditions, spent fuel pool T/H calculations, cooling requirements for dry cask storage, and T/H analysis of long-term disposal.  The acceptable scope of the investigation can include experimental, analytical or numerical examination of the phenomena.

CFD Analysis of Rod Bundles

The session is intended to provide an opportunity for engineers and scientists to present recent developments in applications of CFD to nuclear fuel rod bundle thermal hydraulics. Papers are solicited which deal with any aspect of CFD applications. Types of flow may include: laminar or turbulent, compressible or incompressible, steady or unsteady, and single- or multi-phase flows. A wide range of CFD techniques are encouraged. Techniques may include finite difference/volume, finite elements, large eddy simulation, direct numerical simulation, and vortex simulations. Examples of topics include modeling techniques, turbulence anisotropy phenomena, buoyant flows, evaluation and interpretation of computational results, CFD code comparison and benchmarking, and uncertainty determination.

Two-Phase Flow Experimentation

This Two-Phase Flow Experimentation session includes, but not limited to, experimental studies in the following topics:  Two-phase flow regimes and interfacial structure characterization; Bubble dynamics and interactions, including coalescence and disintegration; Boiling and condensation heat transfer; Critical heat flux phenomena; Two-phase flow instabilities; Two-phase flow in rod bundles; Annular flow entrainment; Experimental methods and advanced instrumentation; Liquid metal two-phase flows; and Emerging two-phase flow applications, including nanofluids.

 

Panels:

Panel on Thermal Hydraulics Aspects of Nuclear Hydrogen Systems

A Next Generation Nuclear Plant (NGNP), Very High Temperature Gas-Cooled Reactor (VHTR) is being developed to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold (1) efficient low cost energy generation and (2) hydrogen production. While hydrogen production and advanced energy cycles are still in its early stages of development, research toward hydrogen production using nuclear process heat is under way.

What this particular panel session would focus on would be the thermal hydraulics aspects of system integration, efficiency, advantages and disadvantages of the high temperature steam electrolysis, S-I process, and hybrid sulfur and other process. This panel invites leading researchers in the nuclear hydrogen production field and the current status of the technology will be discussed. While the focus would be on thermal hydraulics issues, questions on materials, control and safety will also be discussed since these also limit the hydrogen production.

Panel Discussion on Thermal/Hydraulic limits for the Gen-IV Reactors

One of the key features of the Gen-IV reactor designs is the desire to have much higher core exit and operating temperatures.  There are two goals for the high core exit temperatures.  The first goal is to have a nuclear design which can had the same of greater thermodynamic cycle efficiencies as compared to current fossil power plants. This means cycle efficiencies in the 42-48% range as compared to current LWR cycle efficiencies which range from 32 to 36%.  The second goal is to use the high core exit temperatures for the cheaper generation of hydrogen which then can be used for transportation purposes.

High core exit temperatures put a burden on reactor thermal hydraulics, materials, reactor control and safety.  What this particular panel session would focus on would be the thermal hydraulics design and limits for the Gen-IV designs. What new technologies need to be developed to predict these designs and the corresponding limits with confidence or what new improvements in current technologies is needed to have confidence in the prediction of the reactor design and limits While the focus would be on thermal hydraulics issues, questions on materials, control and safety will also be discussed since these also limit the Gen-IV designs.

Panel on Thermal Hydraulic Aspects of Nuclear Hydrogen Systems

A Next Generation Nuclear Plant (NGNP), Very High Temperature Gas-Cooled Reactor (VHTR) is being developed to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold (1) efficient low cost energy generation and (2) hydrogen production. While hydrogen production and advanced energy cycles are still in its early stages of development, research toward hydrogen production using nuclear process heat is under way.

What this particular panel session would focus on would be the thermal hydraulics aspects of system integration, efficiency, advantages and disadvantages of the high temperature steam electrolysis, S-I process, and hybrid sulfur and other process. This panel invites leading researchers in the nuclear hydrogen production field and the current status of the technology will be discussed. While the focus would be on thermal hydraulics issues, questions on materials, control and safety will also be discussed since these also limit the hydrogen production.